ENVIRONMENTAL PROTECTION -2016 ACR-07000-2016 Rev. 0 · ENVIRONMENTAL PROTECTION -2016...

oEnergie NB Power

POINT LEPREAU NUCLEAR GENERATING STATION

Annual Compliance Report

ENVIRONMENTAL PROTECTION - 2016ACR-07000-2016Rev. 0

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Proprietary ACR-07000-2016 Rev. 0

Executive Summary This report describes the 2016 results of the environmental protection program for the Point Lepreau Nuclear Generating Station (PLNGS). In 2016, 1277 samples were analysed to monitor environmental radiation around Point Lepreau and across the province in general. There were 353 other samples, including 208 Quality Assurance (QA) samples. The analyses indicate that radiation dose from PLNGS emissions continues to be well below the public dose limit (1000 microsieverts per annum), and also well below the design and operating target for PLNGS (50 microsieverts per annum).

Source of Dose to the Representative Person Individual Dose (μSv·a-1)

PLNGS airborne emissions 0.85 PLNGS liquid emissions 0.07

Reports are issued to other regulators for non-radioactive hazardous emissions. These reports are described in this report in Section 8. Alignment to the Canadian Standards Association (CSA) standards N288.4-10, Environmental monitoring programs at Class I nuclear facilities and uranium mines and mills and N288.5-11, Effluent monitoring programs at Class I nuclear facilities and uranium mines and mills was progressed in 2016. The following were issued 2016:

• Ecological risk assessment report (Point Lepreau Generating Station- Site Wide Risk Assessment: Human Health and Ecological Risk Assessment, February 2016, Arcadis Canada Inc) as per N288.6-12, Environmental risk assessments at class I nuclear facilities and uranium mines and mills).

• Fish entrainment report (Point Lepreau Generating Station- Final: Entrainment Monitoring Plan and Implementation for Point Lepreau Generating Station, March 2016, Arcadis Canada Inc.).

• Fish impingement report ( NB Power- Progress Report Impingement Monitoring at Point Lepreau Generating Station 2013-2014, March 2016, Arcadis Canada Inc.).

Canadian Nuclear Laboratories (CNL) continued their work to assist the station to close the gaps and implement the standards for PLNGS.

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Table of Contents 1 Introduction ............................................................................................................................ 11

2 PLNGS Radioactive Emission Data ..................................................................................... 13

3 Sample Media, Locations and Frequencies (REMP) .......................................................... 14

4 Summary and Discussion of REMP Data ............................................................................ 25 4.01 Airborne Particulates ...................................................................................................... 26 4.02 Airborne Iodines ............................................................................................................. 29 4.03 Water Vapour .................................................................................................................. 29 4.04 Carbon Dioxide ............................................................................................................... 34 4.05 Ambient Gamma Measurements (TLD) ......................................................................... 38 4.06 Milk ................................................................................................................................. 41 4.07 GEM Particulates (Sr-89,90) .......................................................................................... 42 4.08 Well Water ...................................................................................................................... 44 4.09 Pond/Puddle/Surface Water ............................................................................................ 47 4.10 Berries ............................................................................................................................. 49 4.11 Garden Vegetables .......................................................................................................... 49 4.12 Vegetation (Lichen) ........................................................................................................ 50 4.13 Soil .................................................................................................................................. 54 4.14 Precipitation .................................................................................................................... 56 4.15 Monitoring Well Water, Near Plant ................................................................................ 58 4.16 Seawater .......................................................................................................................... 60 4.17 Tritium and C-14 Analyses of Seafood .......................................................................... 60 4.18 Seafood ........................................................................................................................... 63 4.19 Other Sea Plants .............................................................................................................. 63 4.20 Sediment ......................................................................................................................... 72 4.21 Ambient Gamma Measurements of Intertidal Zone (Ion Chamber) ............................... 74 4.22 LEM Composite Water (Sr-89,90) ................................................................................. 75 4.23 Bore Hole Water, SRWMF ............................................................................................. 75 4.24 Parshall Flume Water, SRWMF ..................................................................................... 80 4.25 Hemlock Knoll Regional Sanitary Landfill Program ..................................................... 84 4.26 Meteorological Data ....................................................................................................... 84

5 Trends (REMP) ...................................................................................................................... 87 5.01 Dose from Airborne and Liquid Pathways ..................................................................... 87 5.02 Tritium (Water Vapour) .................................................................................................. 87 5.03 Cesium-137 (Soil) ........................................................................................................... 90 5.04 Tritium (Monitoring Well Water, Near Plant) .................................................................. 91 5.05 Tritium and C-14 (Seawater) .......................................................................................... 91 5.06 Strontium-90 (LEM Water) ............................................................................................ 92 5.07 Tritium (Parshall Flume Water) ...................................................................................... 93

6 Dose Estimation ...................................................................................................................... 94

7 Quality Assurance Results (REMP) ..................................................................................... 98 7.01 Quality Control Checks .................................................................................................. 98

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7.01.01 Intrinsic Ge Gamma Spectrometer ........................................................................ 99 7.01.02 Beckman LS 6000TA Liquid Scintillation Counter ................................................ 99 7.01.03 Tennelec LB-5100 Gross Alpha/Beta Counter .................................................... 100 7.01.04 Protean WPC 9550 Alpha/Beta Counter ............................................................. 100 7.01.05 Panasonic UD-716AGL and UD-7900U TLD Readers ....................................... 100 7.01.06 Other Instruments ................................................................................................ 100

7.02 External QA .................................................................................................................. 100 7.03 Internal QA ................................................................................................................... 111 7.04 Program Audit ............................................................................................................... 119 7.05 Annual Review ............................................................................................................. 119

8 Non-Radiological Monitoring and Reporting ................................................................... 120 8.01 Ozone Depleting Substance .......................................................................................... 120 8.02 Domestic Waste Water Treatment (Sewage) (Approval to Operate S-2696) ............... 120 8.03 Waste Water Compliance (Approval to Operate I-7479) ............................................. 122 8.04 Air Emission (NPRI) ...................................................................................................... 122 8.05 Chlorine ........................................................................................................................ 123 8.06 Ammonia ...................................................................................................................... 123 8.07 Hydrazine ...................................................................................................................... 123 8.08 EMS Program Audit ..................................................................................................... 123 8.09 Self-Assessments .......................................................................................................... 124

9 Reports and Studies ............................................................................................................. 124

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List of Appendices Appendix A: Statistics, Detection Limits, and Dose at Detection Limits ................................ 125

Appendix B: Sample Collection and Analytical Techniques ................................................... 138

Appendix C: Location Codes .................................................................................................... 145

Appendix D: Abbreviations ...................................................................................................... 152

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List of Figures Figure 3.01: Map of New Brunswick ......................................................................................... 20

Figure 3.02: Air Monitoring Stations ......................................................................................... 21

Figure 3.03: Well Water Sites ..................................................................................................... 22

Figure 3.04: TLD Sites ............................................................................................................... 23

Figure 3.05: Marine Monitoring Sites ........................................................................................ 24

Figure 4.01: Gross Beta (Air Particulates) at Offsite Air Stations ............................................. 28

Figure 4.02: Gross Beta (Air Particulates) at Onsite Air Stations .............................................. 28

Figure 4.03: Tritium (Water Vapour) at Offsite Air Stations ..................................................... 32

Figure 4.04: Tritium (Water Vapour) at Onsite Air Stations ...................................................... 32

Figure 4.05: Gaseous H-3 Emissions for 2016 ........................................................................... 33

Figure 4.06: Gaseous H-3 Emissions and H-3 (Water Vapour) Results ..................................... 33

Figure 4.07: Carbon-14 (Carbon Dioxide) .................................................................................. 37

Figure 4.08: Gaseous C-14 Emissions for 2016 ......................................................................... 37

Figure 4.09: Gaseous C-14 Emissions and C-14 (Carbon Dioxide) Results .............................. 38

Figure 4.10: Mean Ambient Gamma (TLD) Results .................................................................. 41

Figure 4.11: Gross Beta (Well Water) ........................................................................................ 46

Figure 4.12: Tritium (Well Water).............................................................................................. 46

Figure 4.13: Tritium (Pond/Puddle/Surface Water) ...................................................................... 47

Figure 4.14: Cesium-137 (Soil) .................................................................................................. 54

Figure 4.15: Gaseous H-3 Emissions and Tritium (Precipitation) Results ................................... 56

Figure 4.16: Tritium (Monitoring Well Water, Near Plant) ....................................................... 58

Figure 4.17: Liquid H-3 Emissions for 2016 .............................................................................. 61

Figure 4.18: Liquid C-14 Emissions for 2016 ............................................................................ 61

Figure 4.19: Cesium-137 (Sediment) ............................................................................................ 72

Figure 4.20: Liquid Sr-90 Emissions .......................................................................................... 75

Figure 4.21: Tritium (Bore Hole Water, SRWMF) .................................................................... 76

Figure 4.22: Tritium (Parshall Flume Water, SRWMF) ............................................................. 80

Figure 4.23: Wind Rose for Point Lepreau (2016) ..................................................................... 86

Figure 5.01: Dose from Airborne and Liquid Pathways ............................................................. 87

Figure 5.02: Airborne H-3 Emissions ......................................................................................... 88

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Figure 5.03: Tritium (Water Vapour) at Offsite Air Stations ..................................................... 88

Figure 5.04: Tritium (Water Vapour) at Onsite Air Stations ...................................................... 89

Figure 5.05: Cesium-137 (Soil) .................................................................................................. 90

Figure 5.06: Tritium (Monitoring Well Water, Near Plant) ....................................................... 91

Figure 5.07: Liquid H-3 Emissions ............................................................................................. 92

Figure 5.08: Liquid C-14 Emissions ........................................................................................... 92

Figure 5.09: Liquid Sr-90 Emissions .......................................................................................... 93

Figure 5.10: Tritium (Parshall Flume Water) ............................................................................. 93

Figure 6.01: Contribution of Radionuclide to Total Dose (Airborne Pathway)- 2016 ............... 96

Figure 6.02: Contribution of Radionuclide to Total Dose (Liquid Pathway) – 2016 ................. 97

Figure 7.01: Alpha Performance (Internal QA – duplicate/replicate) ...................................... 113

Figure 7.02: Beta Performance (Internal QA – duplicate/replicate) ......................................... 113

Figure 7.03: Beryllium-7 Performance (Internal QA – duplicate/replicate) ............................. 114

Figure 7.04: Carbon-14 Performance (Internal QA – duplicate/replicate) ............................... 114

Figure 7.05: Cobalt-60 Performance (Internal QA – duplicate/replicate) ................................ 115

Figure 7.06: Niobium-95 Performance (Internal QA – duplicate/replicate) ............................. 115

Figure 7.07: Tritium Performance (Internal QA – duplicate/replicate) .................................... 116

Figure 7.08: Potassium-40 Performance (Internal QA – duplicate/replicate) .......................... 116

Figure 7.09: Gamma Performance (Internal QA – duplicate/replicate) ................................... 117

Figure 7.10: Sb-124 Performance (Internal QA – duplicate/replicate) ..................................... 117

Figure 7.11: Strontium-90 Performance (Internal QA – duplicate/replicate) ........................... 118

Figure 7.12: Actinium-228, Cs-137 and Zr-95 Performance (Internal QA – duplicate/replicate) ............................................................................................................................................. 118

Figure 7.13: Gamma Performance (Internal QA - spikes) ........................................................ 119

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List of Tables Table 2.01: Radionuclides Detected in Effluents ....................................................................... 13

Table 3.01: Schedule of Sample Collection and Analysis .......................................................... 15

Table 3.02: Sample Information ................................................................................................. 17

Table 3.03: General Location Codes .......................................................................................... 19

Table 4.01: Airborne Particulates (Bq·m-3) ................................................................................. 27

Table 4.02: Water Vapour (Bq·m3) ............................................................................................. 30

Table 4.03: Tritium (Water Vapour) at Each Air Station (Bq·m-3) ............................................. 31

Table 4.04: Carbon Dioxide (Bq·m-3) ......................................................................................... 35

Table 4.05: Carbon-14 (Carbon Dioxide) at Each Monitoring Location (Bq·m-3) ..................... 36

Table 4.06: Ambient Gamma – TLD (μGy) ............................................................................... 39

Table 4.07: Milk (Bq·L-1) ........................................................................................................... 43

Table 4.08: Well Water (Bq·L-1) ................................................................................................. 45

Table 4.09: Pond/Puddle/Surface Water (Bq·L-1) ....................................................................... 48

Table 4.10: Berries (Bq·kg-1) ....................................................................................................... 51

Table 4.11: Garden Vegetables (Bq·kg-1) .................................................................................... 52

Table 4.12: Vegetation (Bq·kg-1) ................................................................................................. 53

Table 4.13: Soil (Bq·kg-1) ........................................................................................................... 55

Table 4.14: Precipitation (Bq·L-1) ............................................................................................... 57

Table 4.15: Monitoring Well Water, Near Plant (Bq·L-1) ........................................................... 59

Table 4.16: Seawater (Bq·L-1) ..................................................................................................... 62

Table 4.17: Clams, Edible, Raw Mass (Bq·kg-1) ......................................................................... 64

Table 4.18: Dulse, Wet Mass (Bq·kg-1) ....................................................................................... 65

Table 4.19: Fish, Raw Mass (Bq·kg-1) ....................................................................................... 66

Table 4.20: Lobster, Edible, Cooked Mass (Bq·kg-1) .................................................................. 67

Table 4.21: Periwinkles, Edible, Raw Mass (Bq·kg-1) ................................................................ 68

Table 4.22: Aquaculture Salmon, Raw Mass (Bq·kg-1) .............................................................. 69

Table 4.23: Scallops, Raw Mass (Bq·kg-1) .................................................................................. 70

Table 4.24: Sea Plants, Wet Mass (Bq·kg-1) ............................................................................... 71

Table 4.25: Sediment (Bq·kg-1) ................................................................................................... 73

Table 4.26: Ambient Gamma Measurements of Intertidal Zone (Ion Chamber) – (μSv·h-1) .... 74

Table 4.27: Bore Hole Water, SRWMF - Phase 1 (Bq·L-1) ........................................................ 77

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Table 4.30: Parshall Flume Water, SRWMF - Phase 1 (Bq·L-1) ................................................. 81



Table 4.33: Meteorological Data for Point Lepreau (2016) ....................................................... 85

Table 6.01: Annual Dose (2016) ................................................................................................. 95

Table 6.02: Contribution of Radionuclides to Dose in Each Pathway (2015) ............................ 96

Table 7.01: QC Passes & Failures .............................................................................................. 99

Table 7.02: External Quality Assurance Results Outside Expected Range ............................... 102

Table 7.03: External Quality Assurance Frequency ................................................................. 103

Table 7.04: Filter Performance (External QA) ......................................................................... 104

Table 7.06: Charcoal Cartridge Performance (External QA) ................................................... 105

Table 7.07: Milk Performance (External QA) .......................................................................... 105

Table 7.08: Water Performance (External QA) ........................................................................ 107

Table 7.09: Food/Vegetation Performance (External QA) ....................................................... 109

Table 7.10: Soil Performance (External QA) ........................................................................... 110

Table 7.11: Environmental TLD Performance (External QA) ................................................. 111

Table 7.13: Internal Quality Assurance Frequency .................................................................. 112

Table 8.01 Electronic Data Submission to ERRIS ................................................................... 121

Table 8.02 Annual Emissions (2016)........................................................................................ 123

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1 Introduction This document describes the results of the Radiation Environmental Monitoring Program (REMP) and summarizes the reports for non-radioactive hazardous emissions for the year 2016. The REMP is described in IR-03541-HF02, Radiation Environmental Monitoring Program (REMP). The requirement for the REMP is stated in STD-03400-04, Radiation Protection Directives, and SR-79100, Solid Radioactive Waste Management Facility 2007 Safety Report. The underlying reason for the program is the large inventory of radionuclides that are present onsite. The program operates in conjunction with SI-01365-L20, Online Monitoring and Control of Liquid and Airborne Effluents, a program which monitors and controls effluents at their source. The Derived Release Limits (DRLs) are calculated in RD-01364-L1, Derived Release Limits for Radionuclides in Airborne and Liquid Effluents. As part of its overall Management System, PLNGS has an Environmental Management System (EMS) (SI-01365-P101 Developing and Maintaining the Environmental Management System (EMS)) in place that is registered to National Standards of Canada, CAN/CSA-ISO 14004-2004-04 Environmental Management Systems – General Guidelines on Principles, Systems and Support Techniques (2nd Edition). All activities and products that could impact the environment have been identified and logged in a database. From this database, a list of significant environmental aspects (SEAs) was developed and it forms the foundation for the EMS. Management programs are in place for each of the SEAs to ensure compliance with the standards. The SEAs include radiological and non-radiological releases to water and air, waste management and accident management. Environmental assessment and improvement programs have been developed for the SEAs to ensure continual improvement. All activities that support PLNGS are controlled by the PLNGS Management System. The environmental radiation monitoring program falls under the primary process PRR-00660-SU-2 SU-02 Provide Environmental Services. All sub-processes related to routine environmental radiation monitoring come under SU-02. All radionuclide analyses in 2016 were performed in the Fredericton Health Physics Laboratory at 420 York Street, Fredericton, NB. The basis of the REMP complies with National Standards of Canada, CAN/CSA-N288.4-M90 (R2008) Guidelines for Radiological Monitoring of the Environment). Since this standard was replaced in 2010 with CSA standard N288.4-10 Environmental monitoring programs at Class I nuclear facilities, the REMP will be modified to comply with the new standard in 2017. The Radiation Environmental Monitoring Program for PLNGS fulfils several objectives. These are to:

1) permit the estimation of dose to the Representative Person and populations from the radioactive emissions from PLNGS and its Solid Radioactive Waste Management Facility (SRWMF). This estimation of dose is achieved through the analyses of environmental and effluent samples.

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2) provide data to confirm compliance of PLNGS and the SRWMF with release guidelines and regulations and to provide public assurance of compliance. These provisions are achieved through the issuance of the annual report to all interested parties.

3) establish and maintain the capability for environmental monitoring so that an

effective response can be made to emergency conditions. This response is assured by maintaining the resources to step up the monitoring program during increased emissions that are only likely during an accident. The ability to interpret the data and make recommendations is also maintained.

4) maintain a database to facilitate the detection of trends. The database is

maintained by storing all results on a computer system that has the capability of reporting and graphing any desired subsets of the data.

5) verify or refine environmental models used in the calculation of Derived Release

Limits (DRLs). Verification is achieved by comparing the theoretical dispersion factor with one calculated empirically. In addition, other exposure routes to the public are continually evaluated.

6) determine the fate of released radioactive materials to show whether any pathway

to humans has been overlooked. The deposition of radioactive material is determined through the collection and analysis of sample media outside of the established program. In addition, any results that are not consistent with effluent results are investigated.

The capability of the radiation monitoring laboratory is assessed through the QA program and through the daily analytical checks. These checks demonstrate the accuracy and consistency of analyses. The following sections will briefly describe the program. Details are provided on PLNGS emissions, results of analyses, dose estimates, and the quality assurance program.

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2 PLNGS Radioactive Emission Data Emissions from PLNGS continue to be at low levels as indicated in Table 2.01. By the time these emissions reach the edge of the exclusion zone, they are diluted below the detection limits of most analytical procedures.

Table 2.01: Radionuclides Detected in Effluents

Nuclide

Gaseous Effluent

DRL (Bq·a-1)

Emission (Bq) DRL (%)

Liquid Effluent DRL*

(Bq·a-1)

Emission (Bq) DRL (%)*

H-3 2.8E+17 1.5E+14 5.4E-02 4.6E+19 1.8E+14 1.1E-03* C-14 6.8E+15 1.1E+11 1.7E-03 3.3E+14 2.9E+09 1.1E-03* Na-24 ----------- ----------- ----------- 2.2E+15 2.4E+05 1.1E-08*Ar-41 2.6E+17 7.1E+13 2.7E-02 ----------- ----------- -----------Mn-54 ----------- ----------- ----------- 8.1E+13 1.7E+06 1.3E-05*Fe-59 ----------- ----------- ----------- 3.1E+12 2.1E+06 6.6E-05*Co-60 ----------- ----------- ----------- 3.9E+13 9.8E+07 9.1 E-04*Zn-65 ----------- ----------- ----------- 9.7E+12 2.1E+05 2.2E-06*As-76 ----------- ----------- ----------- 1.3E+15 2.4E+05 1.8E-08*

Kr-85m 2.3E+18 1.6E+11 6.7E-06 ----------- ----------- -----------Kr-87 4.1E+17 1.1E+11 2.6E-05 ----------- ----------- -----------Kr-88 1.2E+17 5.7E+11 4.8E-04 ----------- ----------- -----------Sr-90 ----------- ----------- ----------- 6.0E+15 8.3E+04 1.4E-09*Nb-94 ----------- ----------- ----------- 3.7E+14 1.7E+05 4.6E-08*Zr-95 ----------- ----------- ----------- 8.6E+13 3.5E+08 3.2E-03*Nb-95 ----------- ----------- ----------- 8.6E+14 6.8E+08 6.2E-04*

Ag-110m ----------- ----------- ----------- 2.6E+13 9.6E+05 3.6E-06*Sn-113 ----------- ----------- ----------- 4.1E+12 2.2E+06 5.3E-05* Sb-122 ----------- ----------- ----------- 9.4E+14 6.7E+06 7.2E-07* Sb-124 ----------- ----------- ----------- 5.2E+14 2.2E+08 6.3E-05* Sb-125 ----------- ----------- ----------- 1.4E+15 8.7E+06 6.6E-07* I-131 3.7E+13 5.2E+05 1.4E-06 ----------- ----------- -----------

Xe-131m 4.3E+19 1.3E+11 3.0E-07 ----------- ----------- ----------- Xe-133 1.2E+19 4.4E+13 3.9E-04 ----------- ----------- -----------

Xe-133m 1.3E+19 7.0E+11 5.6E-06 ----------- ----------- ----------- Xe-135 1.4 E+18 1.9 E+12 1.3 E-04 ----------- ----------- -----------

Xe-135m 8.6 E+17 1.6 E+11 1.8E-05 ----------- ----------- ----------- Cs-137 ----------- ----------- ----------- 4.6E+14 3.3E+05 7.0E-08* Xe-138 2.9E+17 4.5E+11 1.5E-04 ----------- ----------- ----------- Gd-153 ----------- -------- ----------- 4.2E+15 1.9E+07 6.7E-07* Tb-160 ----------- ----------- ----------- 6.4E+14 2.9E+07 4.5E-06* Alpha ----------- ----------- ----------- ----------- 7.9E+06 ----------- Beta ----------- ----------- ----------- ----------- 7.8E+07 -----------

Nb-97 ----------- ----------- ----------- ----------- 6.0E+10 ----------- Xe-137 ----------- 1.8E+11 ----------- ----------- ----------- -----------

Total 8.5E-02 Total 7.1E-03 * To calculate %DRL for emissions from some locations and during outages, an adjustment is made to compensate for different flow rates.

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3 Sample Media, Locations and Frequencies (REMP) The data contained in this report are for samples collected from January 1 to December 31, 2016, with some overlap for air, precipitation and thermo luminescent dosimeter (TLD) samples. During this time, the major media analysed and their frequency of collection were as indicated in Table 3.01. Sample collection usually takes place at least once each week throughout the year. The number of each sample type collected in 2016 and the major radionuclide measurements performed on that sample type are listed in Table 3.02. The miscellaneous sample group includes those samples that are above and beyond the listed categories or are not routinely collected. Miscellaneous samples include source leak testing and contamination monitoring. The major sample locations are listed in Table 3.03 (details in Appendix C) and shown in Figures 3.01 to 3.05. Each "Indicator" site has a three or four-character identification code (e.g., F01, I10A). An Indicator site is one within the possible influence of PLNGS emissions. A “Reference” site is outside the influence of PLNGS emissions and is identified by the letter R at the end of the location code (e.g., A13R). Sample locations for mobile seafood species (lobster, fish, etc.) caught in the Lepreau area are specified as accurately as reasonably possible. The location of capture, however, may bear little relationship to where the animal has been in the recent past. The availability of such samples is not generally predictable and is outside of the control of the laboratory.

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Table 3.01: Schedule of Sample Collection and Analysis

Sample Medium Typical Frequency Atmospheric Sampling

Airborne Particulates Monthly (integrated sample) Airborne Iodines Monthly (integrated sample) Water Vapour Monthly (integrated sample) Carbon Dioxide Monthly (integrated sample) Ambient Gamma Measurements (TLDs) Quarterly (integrated sample) Gaseous Effluent Monitor (GEM) Particulates Weekly Composite (integrated sample)

Terrestrial Sampling Ambient Gamma Measurements (TLDs) Quarterly (integrated sample) Milk - commercial dairy - dairy farms

Monthly Quarterly

Well Water Semi-annually Pond, Puddle and Surface Water Quarterly Berries Weekly in Season Garden Vegetables Weekly in Season Vegetation Monthly Soil Quarterly Monitoring Well Water (Near Plant) Annually Precipitation Monthly (integrated sample)

Marine Sampling Seawater Quarterly Clams Quarterly When Available Fish Quarterly When Available Lobster Quarterly When Available Periwinkles Monthly When Available Aquaculture Salmon Quarterly When Available Scallops Quarterly When Available Crabs Quarterly When Available Dulse Monthly When Available Other Sea Plants Quarterly Sediment Quarterly Ambient Gamma Measurements of Intertidal Zone (Ion Chamber) Quarterly

Liquid Effluent Monitor (LEM) Composite Water Monthly Composite (integrated sample)

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Table 3.01: Schedule of Sample Collection and Analysis, Continued

Sample Medium Typical Frequency Solid Radioactive Waste Management Facility

Bore Hole Water Three Times Per Year Parshall Flume Water Weekly Ambient Gamma Measurements (TLDs) Quarterly (integrated sample)

Hemlock Knoll Regional Sanitary Landfill Ambient Gamma Measurements (TLDs) Quarterly (integrated sample)

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Table 3.02: Sample Information

Sample Medium Number of Samples Radionuclide Measurements

Atmospheric SamplingAirborne Particulates 95 gamma emitters & gross alpha/betaAirborne Iodines 95 Iodine-130,131,132,133,135 Water Vapour 95 TritiumCarbon Dioxide 35 Carbon-14Ambient Gamma Measurements (TLDs)* 102* gamma exposure

GEM Particulates 51 Strontium-89,90 & gamma emittersTerrestrial Sampling

Ambient Gamma Measurements (TLDs)*

102* gamma exposure

Milk - commercial dairy - dairy farms

12 12 gamma emitters & tritium

Well Water 19 gamma emitters, gross alpha/beta & tritiumPond, Puddle and Surface Water 19 gamma emitters & tritium Berries 4 gamma emittersGarden Vegetables 19 gamma emittersVegetation 16 gamma emittersSoil 40 gamma emittersMonitoring Well Water (Near Plant) 11 gamma emitters & tritium

Precipitation 25 gamma emitters & tritium Marine Sampling

Seawater 16 gamma emitters & tritium Clams 5 gamma emittersFish 7 gamma emittersLobster 7 gamma emittersPeriwinkles 16 gamma emittersAquaculture Salmon 2 gamma emittersScallops 5 gamma emitters Crabs 0 gamma emittersDulse 4 gamma emittersOther Sea Plants 12 gamma emittersSediment 39 gamma emittersAmbient Gamma Measurements of Intertidal Zone (Ion Chamber) 40 gamma exposure

LEM Composite Water 14 Strontium-89,90, gamma emitters, gross alpha/beta

*The same TLD measures gamma dose from radionuclides in the air and on the ground.

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Table 3.02: Sample Information, Continued

Sample Medium Number of Samples Radionuclide Measurements

Solid Radioactive Waste Management Facility Bore Hole Water 100 gamma emitters & tritium Parshall Flume Water 156 gamma emitters & tritium Ambient Gamma (TLDs) 184 gamma exposure

Hemlock Knoll Regional Sanitary Landfill Ambient Gamma (TLDs) 16 gamma exposure

Other Miscellaneous 80 as required Quality Assurance 208 as scheduled

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Table 3.03: General Location Codes

Code Location

A West of Pennfield Ridge B Pennfield to New River Beach (inclusive) C Lepreau and Lepreau Harbour D Little Lepreau and Little Lepreau Basin E Maces Bay F Welch Cove G Pt. Lepreau lighthouse and surrounding area H Duck Cove I PLNGS site – northeast quadrant J PLNGS site – southeast quadrant K PLNGS site – southwest quadrant L PLNGS site – northwest quadrant M PLNGS N Dipper Harbour P East of Dipper Harbour East to Musquash Q Lorneville S Saint John and surrounding area T Taymouth X Fredericton and surrounding area Y Hemlock Knoll Regional Sanitary Landfill

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Figure 3.01: Map of New Brunswick

Cha leur Ba y Baie des C haleurs

Gulf of St LawrenceG olfe du Saint-Laurent

D étroit d

e

Northu m

berland Strai t

B a y

o f F

u n d y B

a i e d e s F u n d y

Île Deer Island Île Campobello Island

Île Grand Manan Island

Edmundston

Fredericton

Saint John

Moncton

Miramichi

Bathurst

Campbellton

Point Lepreau G.S.

0 50 100

kilometresNova Sc otia

Éc osseNouvelle-

Maine

Québec

Île-du-Prince-ÉdouardPrince Edward Island

Nouveau-Brunswic kNew Brunswic k

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Figure 3.02: Air Monitoring Stations

PLGS45 km

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PLGS45 km

3 km

Figure 3.03: Well Water Sites

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PLGS

59 TLDs at the SRWMFare not shown

Figure 3.04: TLD Sites

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Figure 3.05: Marine Monitoring Sites

PLGS28 km

8 km

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4 Summary and Discussion of REMP Data The following is a summary and discussion of the data on environmental samples collected for the year 2016. Most samples contained low levels of naturally occurring K-40 or cosmogenically produced Be-7. Some samples contained Cs-137 (soils, sediments, lichen) from the atmospheric weapons tests of past years and international events (at Chernobyl and Fukushima). Tritium (in air and fresh water) is the only radionuclide originating from PLNGS that is detected consistently. In 2016, analyses that indicated emissions traceable to PLNGS were:

• H-3 in airborne water vapour and fresh water • H-3 in Parshall flume and bore hole water from the Solid Radioactive Waste

Management Facility (SRWMF)

• H-3 in water from onsite monitoring wells The only assessable radiation dose from PLNGS on the local population is that from tritiated water vapour in air. Offsite, the activity of H-3 in air ranges from less than 2E-02 Bq·m-3 (below the lower limit of detection by the method used) to approximately 1E+00 Bq·m-3 of air. The natural concentration of H-3 is up to 7E-01 Bq·L-1 in most surface waters and up to 1E-03 Bq·m-3 in air. The natural concentration of C-14 in the atmosphere is approximately 4E-2 Bq·m-3. This level is usually detected by the sensitive analytical method used in the monitoring program. Only detected radionuclides are listed in the following tables. (Refer to Tables A.01 to A.11 in Appendix A for detailed listings of detection limits. Refer to Appendix C for a listing of location codes.) Most tables contain the following data: Column 1 - Shows the type of analysis or nuclide. Column 2 - Shows the total number of samples analysed. Column 3 – Shows the mean of the Critical Levels (CLs) for all samples. Any measurement greater than the CL is considered detected at the 99% confidence level (an explanation of the statistical protocol is given in Appendix A). Column 4 - Shows the range of the Critical Levels (CLs) for all samples. Any measurement greater than the CL is considered detected at the 99% confidence level (an explanation of the statistical protocol is given in Appendix A). Column 5 - Shows the mean of the detected values (i.e., values exceeding the CL) for all Indicator stations.

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Column 6 - Shows the ratio of the number of detected values to the total number of Indicator samples. Column 7 - Shows the range of detected values for the Indicator stations. Column 8 - Shows the mean of detected values at the Reference location(s). Column 9 - Shows the ratio of detected values to the total number of samples at this location. Column 10 - Shows the range of detected values for the Reference location(s). 4.01 Airborne Particulates Of the 95 filters analyzed, gross alpha was detected on 89, gross beta on 94 and Be-7 on 79. None of these results are attributable to the operation of PLNGS. Air is continuously monitored from the eight locations shown in Figure 3.02. Once a month the filters are changed and analysed. Gross alpha and gross beta measurements are an indication of total activity in the environment. This includes naturally occurring radon progeny, cosmogenic (Be-7), and person-made sources of radiation. The maximum concentration of gross beta in air onsite was 6.0E-04 Bq·m-3 of air. Offsite gross beta reached 1.3E-03 Bq·m-3. When Sr-89,90 emissions are low, the expected concentration of these radionuclides in environmental air samples is below the detection limit. The GEM monitors PLNGS gaseous emissions continuously at their source. The GEM filter was changed weekly. Fifty-one GEM filters were analysed for Sr-89,90. If the weekly emission is more than one percent of the weekly DRL, or if elevated beta activity is detected in environmental air samples, a Sr-89,90 analysis is performed on the environmental air particulate samples. Since no Sr-89 or Sr-90 emissions were detected in 2016, no further analyses were required. Table 4.01 is a summary of detected radionuclides. Figures 4.01 and 4.02 show the gross beta results for each location throughout the year.

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Table 4.01: Airborne Particulates (Bq·m-3)

Analysis Type

Total Number

Critical Level Indicator Locations Reference Locations

Mean Range Mean Frequency Range Mean Frequency Range

ALPHA 95 3.6E-6 1.7E-6 to 1.9E-5 2.1E-5 77/83 4.4E-6 to

8.8E-5 2.3E-5 12/12 7.6E-6 to 7.5E-5

BETA 95 8.8E-6 4.2E-6 to 4.5E-5 2.9E-4 82/83 1.5E-5 to

1.1E-3 3.5E-4 12/12 1.0E-4 to 1.3E-3

Be-7 95 1.5E-4 4.5E-5 to 1.1E-3 1.5E-3 68/83 2.3E-4 to

4.5E-3 1.9E-3 11/12 2.6E-4 to 1.0E-2

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Figure 4.01: Gross Beta (Air Particulates) at Offsite Air Stations

Figure 4.02: Gross Beta (Air Particulates) at Onsite Air Stations

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4.02 Airborne Iodines No radioiodines were detected in any of the 95 samples analysed. Air is monitored continuously, using charcoal cartridges, from the eight locations shown in Figure 3.02. Once a month the cartridges are changed and analysed. Iodine-131 was consistently below the Critical Level (average 1E-05 Bq·m-3). 4.03 Water Vapour Tritium was detected in 76 of the 83 samples collected from the air monitoring stations on the Point Lepreau peninsula, and in one of the 12 samples from the reference location. Water vapour is collected continuously in molecular sieve bombs from the eight locations shown in Figure 3.02. Once a month the bombs are changed and analysed. The maximum concentration of tritium in air onsite was 4.3E+00 Bq·m-3 of air. Offsite it reached 1.2E+00 Bq·m-3. Tritium has been detected occasionally at the reference location, even before PLNGS became operational. Table 4.02 is a summary of the tritium data and Table 4.03 gives details of the tritium results by location. Figures 4.03 and 4.04 show the H-3 results for each location. “Less Than” values are plotted for non-detected results. Generally, locations to the northeast (H04, I01 and N01) have elevated H-3 measurements in the warmer months due to the predominant summer wind direction which influences where the H-3 is detected. This changes in the winter to impact the southwest locations (G02 and L04). When H-3 emissions are low, the expected H-3 concentration in other environmental samples is below the detection limit. If the weekly H-3 emissions are more than one percent of the weekly DRL, a H-3 analysis is performed on berries and garden vegetables. Since the H-3 emissions in 2016 were 5E-02% DRL (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.05 shows the weekly H-3 emissions from PLNGS. Figure 4.06 compares the emissions with the environmental air monitoring results. “Less Than” values are plotted for non-detected results.

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Table 4.02: Water Vapour (Bq·m3)

Analysis Type

Total Number



H-3 95 7.2E-2 3.4E-2 to 1.6E-1 9.3E-1 76/83 4.1E-2 to

4.3E+0 5.5E-2 1/12 5.5E-2 to 5.5E-2

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Table 4.03: Tritium (Water Vapour) at Each Air Station (Bq·m-3)

Location Code A01R/A13R E01 F01 G02 H04 I01 L04 N01

Location Saint Andrews

Maces Bay

Welch Cove

Lepreau Lighthouse

Former Information Centre Site

SRWMF Construction Stores

Dipper Harbour

Distance from PLNGS 47 km 4.5 km 1.6 km 1.0 km 0.75 km 1.2 km 0.55 km 3.7 km

Collection Start Date

The sample collection periods are approximately

one month in duration. All

sample stations are changed at the same time. The start date is the stop date for the previous sample.

2016-01-06 <5.4E-2 4.1E-2 1.2E-1 3.7E-1 1.4E+0 5.7E-1 5.1E-1 9.7E-2

2016-02-02 <4.4E-2 5.1E-2 3.1E-1 8.7E-1 1.3E+0 1.2E+0 4.1E-1 1.7E-1

2016-03-01 5.5E-2 8.9E-2 2.2E-1 8.0E-1 2.2E+0 1.1E+0 1.3E+0 2.7E-1

2016-04-05 <8.2E-2 6.8E-2 2.9E-1 8.2E-1 1.2E+0 1.6E+0 1.1E+0 1.3E-1

2016-05-05 <7.1E-2 9.3E-2 2.2E-1 1.7E-1 1.6E+0 1.2E+0 2.6E+0 3.9E-1

2016-06-08 <7.5E-2 <1.3E-1 2.1E-1 6.8E-1 1.8E+0 2.0E+0 4.2E-1 3.5E-1

2016-07-07 <9.3E-2 <1.1E-1 <1.3E-1 1.9E-1 3.4E+0 2.1E+0 1.1E+0 NA

2016-08-10 <1.6E-1 3.9E-1 7.3E-1 5.4E-1 4.3E+0 2.9E+0 1.8E+0 1.2E+0

2016-09-09 <1.2E-1 <1.2E-1 3.1E-1 6.1E-1 1.8E+0 2.2E+0 1.4E-1 3.1E-1

2016-10-11 <6.8E-2 <6.3E-2 9.7E-2 9.9E-1 8.3E-1 2.9E+0 9.9E-1 1.2E-1

2016-11-08 <5.7E-2 <5.8E-2 9.6E-2 1.4E+0 1.2E+0 1.6E+0 2.1E+0 1.6E-1

2016-12-06 <4.1E-2 <3.8E-2 1.7E-1 4.8E-1 8.7E-1 9.4E-1 1.1E+0 8.5E-2

NA: Data not available due to equipment failure.

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Figure 4.03: Tritium (Water Vapour) at Offsite Air Stations

Figure 4.04: Tritium (Water Vapour) at Onsite Air Stations

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Note: The Weekly DRL for H-3 is 5.4E+15 Bq

Figure 4.05: Gaseous H-3 Emissions for 2016

Figure 4.06: Gaseous H-3 Emissions and H-3 (Water Vapour) Results

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4.04 Carbon Dioxide Carbon-14 was detected in 13 of the 24 samples from the onsite monitors and six of the 11 samples from the offsite monitor. Air is continuously bubbled through a caustic solution at two onsite locations (G02 and H04 in Figure 3.02) and at one reference location. The caustic bubblers are changed monthly and returned to the lab for analysis. The maximum concentration of gaseous C-14 onsite was less than 1.0E-01 Bq·m-3. Offsite the gaseous C-14 concentration was less than 1.9E-01 Bq·m-3. Based on stack emissions, the calculated incremental concentration of C-14 in air at the boundary fence for 2016 was less than 5E-04 Bq·m-3 (a small fraction of the natural level of 4E-02 Bq·m-3). A summary of the analysis results is given in Table 4.04. Table 4.05 gives details of C-14 results (graphically shown in Figure 4.07). When C-14 emissions are low, the expected concentration of C-14 in other environmental samples is below the detection limit. If the weekly C-14 emission is more than one percent of the weekly DRL, a C-14 analysis is performed on berries, milk, water and garden vegetables. Since the C-14 emissions in 2016 were 1.7E-03% DRL (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.08 shows the weekly C-14 emissions from PLNGS. Figure 4.09 compares the emissions with the environmental air monitoring results. “Less Than” values are plotted for non-detected results.

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Table 4.04: Carbon Dioxide (Bq·m-3)

Analysis Type

Total Number



C-14 35 3.7E-2 2.0E-2 to 1.8E-1 4.2E-2 13/24 2.9E-2 to

6.5E-2 4.1E-2 6/11 3.6E-2 to 4.3E-2

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Table 4.05: Carbon-14 (Carbon Dioxide) at Each Monitoring Location (Bq·m-3)

Location Code G02 H04 X03R

Location Lepreau Lighthouse Former Information Centre Site Fredericton Laboratory

Distance from PLNGS 1.0 km 0.75 km 100 km

Collection Start Date The sample collection periods are

approximately one month in duration. All sample stations are changed at the same time. The start date is the stop date for the

previous sample.

2016-01-06 <3.6E-2 <4.7E-2 4.3E-2

2016-02-02 <4.9E-2 3.5E-2 4.3E-2

2016-03-01 4.4E-2 3.5E-2 4.0E-2

2016-04-05 4.2E-2 3.4E-2 <3.6E-2

2016-05-05 6.5E-2 3.6E-2 4.1E-2

2016-06-08 <5.7E-2 <5.3E-2 <5.9E-2

2016-07-07 4.7E-2 <5.9E-2 4.3E-2

2016-08-10 <5.8E-2 <6.0E-2 3.6E-2

2016-09-09 5.3E-2 <7.7E-2 <8.1E-2

2016-10-11 4.1E-2 <1.9E-1 <1.0E-1

2016-11-08 <6.6E-2 4.3E-2 <5.9E-2

2016-12-06 2.9E-2 4.3E-2 NA

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Figure 4.07: Carbon-14 (Carbon Dioxide)

Note: The Weekly DRL for C-14 is 1.3E+14 Bq

Figure 4.08: Gaseous C-14 Emissions for 2016

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Figure 4.09: Gaseous C-14 Emissions and C-14 (Carbon Dioxide) Results 4.05 Ambient Gamma Measurements (TLD) Gamma exposure measurements were slightly elevated onsite compared with offsite. The elevated measurements were at the locations near the SRWMF and reactor building. Ambient gamma radiation is measured by TLDs at the 76 locations shown in Figure 3.04. Forty-six of these locations are near the SRWMF. TLDs are changed quarterly. None of the 302 dosimeters placed in the environment were lost or damaged. Dosimeters were not placed in the new location (A13R), which was added in late 2015, until after the second quarter. The average measurement at the SRWMF (987 μGy·a-1) is higher than for other onsite locations (739 μGy·a-1) and boundary locations (724 μGy·a-1). The measurements at other onsite locations are not significantly different from those at offsite locations (733 μGy·a-1) and that at the reference location (688 μGy·a-1). A location was added in 2001 in a community (York Mills) 120 km north west of PLNGS. The area is noted for its natural uranium content and the measurement at this site (1364 μGy·a-1) is higher than the highest location at PLNGS. Data are given in Table 4.06. Increases in measurements at the SRWMF locations (I11A to I11T on the perimeter fence of the SRWMF-Phase 1, I21A to I21L on the perimeter fence of the SRWMF-Phase 2 and I31A to I31T on the perimeter fence of the SRWMF-Phase 3) are due to low-level waste, used fuel emplacement and refurbishment waste, and not to station emissions. There were 190 concrete canisters filled to the end of 2016 with 102,598 used-fuel bundles. A small, but indefinable, portion of the measurement on the TLDs at the SRWMF is due to enhanced natural

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radiation from the aggregate used in making the concrete structures. Figure 4.10 compares the reference location results with the results for other locations.

Table 4.06: Ambient Gamma – TLD (μGy)

Location Dose (μGy+ 10%)1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year

A13R NA NA 175 ± 18 169 ± 17 690 ± 20 B03 195 ± 20 172 ± 17 170 ± 17 156 ± 16 690 ± 30 C03 223 ± 22 205 ± 21 207 ± 21 194 ± 19 830 ± 40 D02 195 ± 20 180 ± 18 190 ± 19 176 ± 18 740 ± 40 E01 171 ± 17 163 ± 16 166 ± 17 153 ± 15 650 ± 30 E04 193 ± 19 193 ± 19 187 ± 19 178 ± 18 750 ± 40 E05 182 ± 18 165 ± 16 214 ± 21 164 ± 16 720 ± 40 E06 265 ± 27 237 ± 24 254 ± 25 231 ± 23 990 ± 50 F01 151 ± 15 135 ± 13 134 ± 13 123 ± 12 540 ± 30 G02 210 ± 21 188 ± 19 194 ± 19 176 ± 18 770 ± 40 H04 187 ± 19 149 ± 15 166 ± 17 146 ± 15 650 ± 30 H05 102 ± 11 133 ± 13 140 ± 14 118 ± 12 490 ± 20 I11A 240 ± 24 236 ± 24 261 ± 26 224 ± 22 960 ± 50 I11B 245 ± 24 246 ± 25 255 ± 26 228 ± 23 970 ± 50 I11C 242 ± 24 232 ± 23 231 ± 23 217 ± 22 920 ± 50 I11D 237 ± 24 226 ± 23 246 ± 25 224 ± 22 930 ± 50 I11E 254 ± 25 236 ± 24 248 ± 25 229 ± 23 970 ± 50 I11F 279 ± 28 263 ± 26 361 ± 36 315 ± 31 1220 ± 60 I11J 255 ± 25 235 ± 23 249 ± 25 223 ± 22 960 ± 50 I11K 233 ± 23 229 ± 23 240 ± 24 223 ± 22 930 ± 50 I11L 230 ± 23 236 ± 24 235 ± 23 219 ± 22 920 ± 50 I11M 309 ± 31 248 ± 25 327 ± 33 279 ± 28 1160 ± 60 I11N 245 ± 24 233 ± 23 319 ± 32 261 ± 26 1060 ± 50 I11O 237 ± 24 234 ± 23 435 ± 44 238 ± 24 1150 ± 60 I11P 257 ± 26 248 ± 25 576 ± 58 253 ± 25 1330 ± 70 I11Q 250 ± 25 232 ± 23 331 ± 33 275 ± 27 1090 ± 50 I11S 238 ± 24 228 ± 23 248 ± 25 234 ± 23 950 ± 50 I11T 263 ± 26 263 ± 26 266 ± 27 247 ± 25 1040 ± 50 I21A 227 ± 23 201 ± 20 218 ± 22 196 ± 20 840 ± 40 I21B 241 ± 24 224 ± 22 246 ± 25 243 ± 24 950 ± 50 I21C 248 ± 25 209 ± 21 244 ± 24 206 ± 21 910 ± 50 I21D 302 ± 30 290 ± 29 290 ± 29 268 ± 27 1150 ± 60 I21E 286 ± 29 273 ± 27 276 ± 28 272 ± 27 1110 ± 60 I21F 218 ± 22 198 ± 20 215 ± 21 230 ± 23 860 ± 40 I21G 231 ± 23 203 ± 20 213 ± 21 206 ± 21 850 ± 40 I21H 254 ± 25 221 ± 22 230 ± 23 216 ± 22 920 ± 50

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Table 4.06 (continued): Ambient Gamma – TLD (μGy)

Location Dose (μGy+ 10%)

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year I21I 224 ± 22 206 ± 21 210 ± 21 218 ± 22 860 ± 40 I21J 285 ± 28 223 ± 22 211 ± 21 203 ± 20 920 ± 50 I21K 228 ± 23 222 ± 22 223 ± 22 203 ± 20 880 ± 40 I21L 236 ± 24 196 ± 20 214 ± 21 201 ± 20 850 ± 40 I31A 211 ± 21 211 ± 21 228 ± 23 225 ± 22 870 ± 40 I31B 236 ± 24 225 ± 23 234 ± 23 221 ± 22 920 ± 50 I31C 256 ± 26 236 ± 24 242 ± 24 243 ± 24 980 ± 50 I31D 261 ± 26 251 ± 25 257 ± 26 259 ± 26 1030 ± 50 I31E 267 ± 27 257 ± 26 257 ± 26 252 ± 25 1030 ± 50 I31F 283 ± 28 263 ± 26 269 ± 27 255 ± 25 1070 ± 50 I31G 275 ± 27 251 ± 25 284 ± 28 264 ± 26 1070 ± 50 I31H 262 ± 26 264 ± 26 260 ± 26 251 ± 25 1040 ± 50 I31I 246 ± 25 248 ± 25 252 ± 25 241 ± 24 990 ± 50 I31J 263 ± 26 249 ± 25 248 ± 25 246 ± 25 1010 ± 50 I31K 266 ± 27 247 ± 25 224 ± 22 240 ± 24 980 ± 50 I31L 246 ± 25 230 ± 23 233 ± 23 226 ± 23 940 ± 50 I31M 251 ± 25 233 ± 23 241 ± 24 228 ± 23 950 ± 50 I31N 252 ± 25 232 ± 23 236 ± 24 228 ± 23 950 ± 50 I31P 271 ± 27 249 ± 25 255 ± 26 241 ± 24 1020 ± 50 I31Q 267 ± 27 252 ± 25 261 ± 26 243 ± 24 1020 ± 50 I31S 257 ± 26 249 ± 25 257 ± 26 233 ± 23 1000 ± 50 I31T 252 ± 25 211 ± 21 225 ± 22 222 ± 22 910 ± 50 I86 213 ± 21 176 ± 18 180 ± 18 180 ± 18 750 ± 40 I87 183 ± 18 175 ± 17 177 ± 18 216 ± 22 750 ± 40 I88 196 ± 20 175 ± 18 180 ± 18 169 ± 17 720 ± 40 I89 202 ± 20 175 ± 17 178 ± 18 169 ± 17 720 ± 40 J20 224 ± 22 188 ± 19 200 ± 20 197 ± 20 810 ± 40 J35 232 ± 23 195 ± 19 196 ± 20 190 ± 19 810 ± 40 K01 217 ± 22 213 ± 21 193 ± 19 215 ± 21 840 ± 40 L01 265 ± 27 191 ± 19 199 ± 20 185 ± 18 840 ± 40 L03 171 ± 17 203 ± 20 224 ± 22 200 ± 20 800 ± 40 L04 196 ± 20 194 ± 19 209 ± 21 186 ± 19 790 ± 40 M02 151 ± 15 126 ± 13 148 ± 15 130 ± 13 550 ± 30 N01 186 ± 19 170 ± 17 177 ± 18 166 ± 17 700 ± 40 P03 176 ± 18 196 ± 20 173 ± 17 161 ± 16 710 ± 40 X12 358 ± 36 352 ± 35 343 ± 34 310 ± 31 1360 ± 70

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Table 4.06: Ambient Gamma – TLD (μGy), Continued

Location Dose (μGy+ 10%)

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year YTL1 140 ± 14 138 ± 14 132 ± 13 126 ± 13 540 ± 30 YTL2 166 ± 17 139 ± 14 154 ± 15 151 ± 15 610 ± 30 YTL3 139 ± 14 121 ± 12 129 ± 13 109 ± 11 500 ± 20 YTL4 134 ± 13 123 ± 12 128 ± 13 112 ± 11 500 ± 20

NA: Data Not Available – New location established after second quarter.

Figure 4.10: Mean Ambient Gamma (TLD) Results 4.06 Milk Of the 24 samples analysed, K-40 was detected in 23, and H-3 in six. None of these results are attributable to the operation of PLNGS (the H-3 results were deemed false positives). There are no commercial herds or individual cows producing milk in the Lepreau area. The closest herds to PLNGS are in Lynnfield (70 km to the northwest), Fredericton Junction (70 km to the north), and Hammond River (60 km to the northeast). Milk from these locations is analysed quarterly. Milk from a commercial dairy is purchased each month from a supermarket in Fredericton. All milk samples are analysed for gamma emitting radionuclides and tritium.

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Since C-14 emissions are low, the expected concentration of C-14 in milk is below the detection limit. If the weekly C-14 emissions are more than one percent of the weekly DRL, a C-14 analysis is performed on milk. Since the C-14 emissions in 2016 were 1.7E-03% DRL (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.08 shows the weekly C-14 emissions. Naturally occurring K-40 (average of 5.6E+01 Bq·L-1) was also detected in milk. PLNGS emissions of tritium and gamma emitters were too low throughout the year to be detected in these milk samples. The six detected tritiums were deemed false positives. Table 4.07 is a summary of the detected radionuclides in milk. 4.07 GEM Particulates (Sr-89,90) When Sr-89,90 emissions are low, the expected concentration of Sr-89,90 in environmental air samples is below the detection limit. The GEM monitors PLNGS gaseous emissions continuously at their source. The GEM filter is changed weekly and is sent to the Fredericton lab for analysis. Fifty-one of these GEM filters were analysed for Sr-89,90. If the weekly emissions are more than one percent of the weekly DRL, or if elevated beta activity is detected in environmental air samples, a Sr-89,90 analysis is performed on these environmental air samples. Since no Sr-89 or Sr-90 emissions were detected in 2016, no further analyses were required.

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Table 4.07: Milk (Bq·L-1)

Analysis Type

Total Number



H-3 24 1.3E+1 1.2E+1 to 1.4E+1 1.5E+1 3/12 1.2E+1 to

1.7E+1 2.4E+1 3/12 1.4E+1 to 3.8E+1

K-40 24 7.0E-1 2.9E-1 to 3.7E+0 5.5E+1 11/12 4.8E+1 to

6.0E+1 5.7E+1 12/12 4.6E+1 to 5.9E+1

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4.08 Well Water Of the 19 samples analysed, gross alpha was detected in eight, gross beta was detected in 15 and H-3 in five. Only the H-3 results are attributable to the operation of PLNGS. Water is collected semi-annually from the 10 locations shown in Figure 3.03. Two of these wells are onsite. Up to ten additional wells are sampled once per year. These wells are located just outside the exclusion boundary and belong to local residents. The alpha (up to 1.2E+00 Bq·L-1) and beta (up to 9.1E-01 Bq·L-1) activities are due to the presence of naturally occurring radionuclides particular to certain locations. Detected H-3 concentrations ranged from 1.6E+01 to 2.9E+01 Bq·L-1. Tritium from PLNGS emissions washes out into precipitation and subsequently drains into some of the wells. Precipitation analyses (Section 4.14) indicate H-3 concentrations ranging from 1.5E+01 to 4.1E+02 Bq·L-1 in 21 of 25 samples. Since C-14 emissions are low, the expected concentration of C-14 in well water is below the detection limit. If the weekly C-14 emissions are more than one percent of the weekly DRL, a C-14 analysis is performed on well water. Since the C-14 emissions in 2016 were 1.7E-03% DRL (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.08 shows the weekly C-14 emissions. Table 4.08 is a summary of the detected radionuclides in well water. Figures 4.11 and 4.12 show the gross beta and H-3 results for each sample. “Less Than” values are plotted for non-detected results. The H-3 measurements were made after samples had been allowed to sit for up to two weeks to reduce radioactive interference from the relatively abundant, but short half-life, radon progeny which are common in most well waters. The Health Canada, 2010 Guidelines for Canadian Drinking Water Quality (Federal-Provincial-Territorial Committee on Drinking Water of the Federal-Provincial-Territorial Committee on Health and the Environment) recommends 7.0E+03 Bq·L-1 as the maximum acceptable average concentration for H-3 in drinking water.

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Table 4.08: Well Water (Bq·L-1)

Analysis Type

Total Number



ALPHA 19 7.0E-2 2.6E-2 to 1.3E-1 2.4E-1 8/19 6.9E-2 to

1.2E+0 * * *

BETA 19 4.9E-2 3.0E-2 to 6.9E-2 2.1E-1 15/19 4.0E-2 to

9.1E-1 * * *

H-3 19 1.3E+1 1.2E+1 to 1.4E+1 2.2E+1 5/19 1.6E+1 to

2.9E+1 * * *

*There is no reference location.

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Figure 4.11: Gross Beta (Well Water)

Figure 4.12: Tritium (Well Water)

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4.09 Pond/Puddle/Surface Water Low levels of H-3 were detected in 10 of the 19 samples. No gamma emitters were detected in these samples. This category includes ponds, lakes, streams and runoff samples. Most of these samples are from onsite locations. Two important offsite locations, sampled quarterly, are the freshwater supply reservoirs for Saint John and PLNGS, at Spruce Lake and Hanson Stream, respectively. Detected H-3 activities ranged from 1.9E+01 to 9.8E+01 Bq·L-1. Variability can be due to the size of the water reservoir and the length of time the sample has remained at the location. Tritium from PLNGS emissions washes out into precipitation. Precipitation analyses (Section 4.14) indicate H-3 concentrations ranging from 1.5E+01 to 4.1E+02 Bq·L-1 in 21 of 25 samples. Since C-14 emissions are low, the expected concentration of C-14 in water is below the detection limit. If the weekly C-14 emissions are more than one percent of the weekly DRL, a C-14 analysis is performed on water. Since the C-14 emissions in 2016 were 1.7E-03% DRL (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.08 shows the weekly C-14 emissions. Table 4.09 is a summary of the detected radionuclides in surface water. Figure 4.13 shows H-3 results for each location. “Less Than” values are plotted for non-detected results.

Figure 4.13: Tritium (Pond/Puddle/Surface Water)

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Table 4.09: Pond/Puddle/Surface Water (Bq·L-1)

Analysis Type

Total Number



H-3 19 1.4E+1 1.2E+1 to 1.6E+1 4.7E+1 10/19 1.9E+1 to

9.8E+1 * * *


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4.10 Berries Potassium-40 was detected in one of the four samples analysed. This result is not attributable to the operation of PLNGS. Berries are sampled weekly when in season. Three samples of blueberries were collected from Pennfield and one sample of blackberries was collected from Dipper Harbour. As in most food samples, naturally occurring K-40 was detected in one of the four samples (9.2E+01 Bq·kg-1). Since H-3 and C-14 emissions are low, the expected concentrations of H-3 and C-14 in berries are below the detection limits. If the H-3 or C-14 weekly emissions are more than one percent of the weekly DRL, then H-3 or C-14 analysis is performed on berries. Since the emissions in 2016 were 5E-02% DRL for H-3 and 2E-03% DRL for C-14 (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.05 shows the weekly H-3 emissions and Figure 4.08 shows the weekly C-14 emissions. Table 4.10 is a summary of the detected radionuclides in berries. 4.11 Garden Vegetables Potassium-40 was detected in 17 of the 19 samples analysed. These results are not attributable to the operation of PLNGS. All samples were taken from a local garden in Dipper Harbour (4 km from PLNGS in the predominant downwind direction). These samples were supplied weekly during the growing season. As in most food samples, naturally occurring K-40 was detected in 17 of the 19 samples (5.8E+01 to 3.4E+02 Bq·kg-1). Since H-3 and C-14 emissions are low, the expected concentrations of H-3 and C-14 in garden vegetables are below the detection limit. If the H-3 or C-14 weekly emissions are more than one percent weekly DRL, then H-3 or C-14 analysis is performed on garden vegetables. Since the emissions in 2016 were 5E-02% DRL for H-3 and 2E-03% DRL for C-14 (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.05 shows the weekly H-3 emissions and Figure 4.08 shows the weekly C-14 emissions. Table 4.11 is a summary of the detected radionuclides in garden vegetables.

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4.12 Vegetation (Lichen) Of the 16 samples analysed, Be-7 was detected in 12 and K-40 in two. These results are not attributable to the operation of PLNGS. These samples are collected whenever and wherever available from onsite locations. Different species of lichen and moss concentrate a wide range of radionuclides and are sensitive indicators of radionuclides in the environment. Cosmogenically produced Be-7 was detected in 12 samples (2.1E+02 to 4.8E+02 Bq·kg-1). As in most organic samples, naturally occurring K-40 was detected in 2 of the 16 samples (2.7E+02 to 7.2E+02 Bq·kg-1). Table 4.12 is a summary of the detected radionuclides in vegetation.

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Table 4.10: Berries (Bq·kg-1)

Analysis Type

Total Number



K-40 4 3.9E+1 2.7E+1 to 5.3E+1 9.2E+1 1/4 9.2E+1 to

9.2E+1 * * *


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Table 4.11: Garden Vegetables (Bq·kg-1)

Analysis Type

Total Number



K-40 19 3.2E+1 5.2E+0 to 1.7E+2 1.6E+2 17/19 5.8E+1 to

3.4E+2 * * *


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Table 4.12: Vegetation (Bq·kg-1)

Analysis Type

Total Number



Be-7 16 8.9E+1 3.2E+1 to 2.0E+2 3.0E+2 12/16 2.1E+2 to

4.8E+2 * * *

K-40 16 2.4E+2 7.0E+1 to 5.1E+2 4.9E+2 2/16 2.7E+2 to

7.2E+2 * * *


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4.13 Soil Of the 40 samples analysed, Cs-137 was detected in 16, Ac-228 in 30 and K-40 in 39. These results are not attributable to the operation of PLNGS. Soil samples are taken quarterly from the eight air monitoring location sites shown in Figure 3.02 and from the local elementary school. Samples are collected at E02 rather than E01 due to a lack of readily available soil at that site. Thirty-nine samples contained naturally occurring K-40 (3.3E+02 to 1.4E+03 Bq·kg-1), 30 samples contained naturally occurring Ac-228 (1.4E+01 to 6.9E+01 Bq·kg-1) and 16 samples contained Cs-137 (1.6E+00 to 4.5E+01 Bq·kg-1) . All Cs-137 results were at typical levels for the region. Cesium-137 from fallout of past atmospheric weapons tests and international events tends to accumulate in the organic layer of the soil. Most fluctuation in Cs-137 and K-40 levels seems to be due to the quantity of organic load in the sample. Table 4.13 is a summary of the detected radionuclides in soil. Figure 4.14 shows individual Cs-137. “Less Than” values are plotted for non-detected results.

Figure 4.14: Cesium-137 (Soil)

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Table 4.13: Soil (Bq·kg-1)

Analysis Type

Total Number



Cs-137 40 1.6E+0 8.2E-1 to 6.4E+0 1.0E+1 15/36 1.6E+0 to

4.3E+1 4.5E+1 1/4 4.5E+1 to 4.5E+1

Ac-228 40 4.9E+0 1.8E+0 to 3.4E+1 3.6E+1 26/36 1.4E+1 to

6.9E+1 3.4E+1 4/4 2.9E+1 to 3.9E+1

K-40 40 2.0E+1 5.1E+0 to 8.6E+1 7.0E+2 35/36 3.3E+2 to

1.4E+3 6.6E+2 4/4 5.0E+2 to 7.9E+2

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4.14 Precipitation Of the 25 samples analysed, H-3 was detected in 21 and Be-7 in one.. The H-3 results are attributable to the operation of PLNGS. Precipitation is collected continuously at the four onsite air monitoring stations (locations shown in Figure 3.02). The samples are changed approximately monthly, depending on rainfall and freeze up. Detected H-3 levels spanned 1.5E+01 to 4.1E+02 Bq·L-1. Samples taken during periods of heavy rainfall have lower H-3 levels due to dilution. Cosmogenically produced Be-7 was detected in one sample (3.2E+00 Bq·L-1). Since C-14 emissions are low, the expected concentration of C-14 in water is below the detection limit. If the C-14 weekly emissions are more than one percent of the weekly DRL, a C-14 analysis is performed on water. Since the C-14 emissions in 2016 were 1.7E-03% DRL (and in no week exceeded one percent of the weekly DRL), no further analyses were required. Figure 4.08 shows the weekly C-14 emissions. Table 4.14 is a summary of the detected radionuclides in precipitation. Figures 4.03 and 4.04 show average monthly H-3 results and Figure 4.05 shows gaseous H-3 emission. Figure 4.15 shows average monthly H-3 results and gaseous H-3 emission. “Less Than” values are plotted for non-detected results.

Figure 4.15: Gaseous H-3 Emissions and Tritium (Precipitation) Results

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Table 4.14: Precipitation (Bq·L-1)

Analysis Type

Total Number



H-3 25 1.3E+1 1.2E+1 to 1.4E+1 1.0E+2 21/25 1.5E+1 to

4.1E+2 * * *

Be-7 25 2.7E+0 1.4E+0 to 4.9E+0 3.2E+0 1/25 3.2E+0 to

3.2E+0 * * *


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4.15 Monitoring Well Water, Near Plant Low levels of H-3 were detected in all samples analysed. These results are attributable to PLNGS emissions. Eleven monitoring wells are sampled once per year. This frequency will be increased for some or all wells if H-3 concentrations greater than 7000 Bq·L-1 are detected. As well, additional samples may be collected if an abnormal release is suspected or an elevated result is obtained. Tritium concentrations averaged 1.4E+02 Bq·L-1, ranging up to 2.2E+02 Bq·L-1. Table 4.15 is a summary of the detected radionuclides in monitoring well water. Figure 4.16 shows individual H-3 results. “Less Than” values are plotted for non-detected results.

Figure 4.16: Tritium (Monitoring Well Water, Near Plant)

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Table 4.15: Monitoring Well Water, Near Plant (Bq·L-1)

Analysis Type

Total Number



H-3 11 1.3E+1 1.2E+1 to 1.4E+1 1.4E+2 11/11 4.4E+1 to

2.2E+2 * * *


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4.16 Seawater Potassium-40 was detected in 14 of the 16 samples analysed and H-3 was detected in three. The H-3 results are attributable to the operation of PLNGS. Seawater is collected quarterly from three locations close to PLNGS and one reference location near Saint John (shown in Figure 3.05). Naturally occurring K-40 was detected (9.0E+00 to 1.5E+01 Bq·L-1) in 14 samples. Tritium was detected in three (1.3E+01 to 1.6E+01 Bq·L-1). Calculations suggest that the 2016 average concentration of tritium in seawater, due to emissions from PLNGS in the liquid pathway (see Figure 4.17), would be about 1E+01 Bq·L-1 at the out-fall (samples are not collected at this point, but are taken at the shoreline nearby). This calculation takes into account the total tritium released over the year, the flow rate of the condenser cooling water (about 2.5E+01 m3·s-1), and tidal mixing. A dilution factor of 20 is assumed for tidal mixing at the out-fall during normal coolant flows. For collection further away from the outfall, a tidal mixing factor of 40, or even higher, is more realistic. A factor of 40 would result in an average H-3 concentration of about 9E-01 Bq·L-1 in seawater during 2016 at the H03 location. In past years, when samples were taken soon after pump out of higher than usual amounts of H-3, the results were much less than the predicted levels. These results further confirm the conservatism in the calculation. When C-14 and Sr-89,90 emissions are low, the expected concentration of these radionuclides in seawater is below the detection limit. If the monthly emissions are more than one percent of the monthly DRL, a C-14 or Sr-89,90 analysis is performed on seawater. Since the liquid emissions in 2016 were 1E-03% DRL for C-14 and 1E-09% DRL for Sr-90 (and in no month exceeded one percent of the monthly DRL), no further analyses were required. Strontium-89 was not detected in releases. Figure 4.18 shows the monthly C-14 emissions. Table 4.16 is a summary of the detected radionuclides in seawater. 4.17 Tritium and C-14 Analyses of Seafood When H-3 and C-14 emissions are low, the expected concentrations of these radionuclides in seafood are below the detection limit. If the monthly emissions are more than one percent of the monthly DRL, a H-3 or C-14 analysis is performed on seafood. Since the emissions in 2016 were 1E-03% DRL for H-3 and 1E-03% DRL for C-14 (and in no month exceeded one percent of the monthly DRL), no further analyses were required. Figures 4.17 and 4.18 show the emissions of these radionuclides.

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Note: The Monthly DRL for H-3 is 3.8E+18 Bq

Figure 4.17: Liquid H-3 Emissions for 2016

Note: The Monthly DRL for C-14 is 2.7E+13 Bq

Figure 4.18: Liquid C-14 Emissions for 2016

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Table 4.16: Seawater (Bq·L-1)

Analysis Type

Total Number



H-3 16 1.3E+1 1.2E+1 to 1.4E+1 1.4E+1 3/12 1.3E+1 to

1.6E+1 * * *

K-40 16 2.9E+0 7.8E-1 to 7.3E+0 1.3E+1 10/12 1.0E+1 to

1.6E+1 1.2E+1 4/4 9.0E+0 to 1.5E+1

* The activity is less than or equal to the Critical Level ( 99 % Confidence Level).

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4.18 Seafood Potassium-40 is usually detected in these samples. The results are not attributable to the operation of PLNGS. Figure 3.05 shows the locations for most of these samples. Clams – Four samples were collected from Deer Island and one from the Lepreau area. The inshore fishery often faces restrictions placed upon the harvesting of shellfish, either for conservation of stocks or because of bacterial contamination or algal blooms. The restrictions affect the availability of these sample types for analysis. Data are shown in Table 4.17. Crab - As in most years, there was no active crab fishery in the local area. No samples were collected in 2016. Dulse - Dulse is an edible seaweed that is a popular snack food in the area. Four samples were collected (two from the Lepreau area and two from Grand Manan). Data are shown in Table 4.18. Fish - The fish category now tends to be made up of haddock and halibut, if they are available at all. Seven samples were collected in 2016 (three from the Lepreau area and four from unknown locations in the Bay of Fundy). Data are shown in Table 4.19. Lobster – Seven samples were collected from the Lepreau area. A few lobster are obtained during each of the two federally regulated fishing seasons per year. Data are shown in Table 4.20. Periwinkles – Sixteen samples were collected from the Lepreau area. Data are shown in Table 4.21. Aquaculture Salmon - The aquaculture salmon industry is important to the area west of PLNGS. Late in 2004, a new facility close to the PLNGS outfall in Duck Cove began operation. The fish were removed from here in 2007, and were restocked in 2008. No samples were available in 2016 from this facility, so two samples were collected from Beaver Harbour. Data are shown in Table 4.22. Scallops - Five samples were collected from the Lepreau area. Data are shown in Table 4.23. 4.19 Other Sea Plants Potassium-40 was detected in all 12 samples analysed. These results are not attributable to the operation of PLNGS. Sea plants other than dulse are analysed. Various species of seaweed (for example, Ascophylum) occur on the rocks on the Point Lepreau peninsula and are collected quarterly. Sample locations are shown in Figure 3.05. Naturally occurring K-40 ranged from 2.3E+02 to 5.2E+02 Bq·kg-1. Data are shown in Table 4.24.

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Table 4.17: Clams, Edible, Raw Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 5 1.3E+2 4.7E+1 to 1.6E+2 1.9E+2 2/5 1.7E+2 to

2.0E+2 * * *

*There were no reference samples.

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Table 4.18: Dulse, Wet Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 4 3.5E+1 1.4E+1 to 8.1E+1 5.1E+2 2/2 3.3E+2 to

6.9E+2 3.4E+2 2/2 3.1E+2 to 3.6E+2

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Table 4.19: Fish, Raw Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 7 2.3E+1 1.1E+1 to 7.1E+1 1.5E+2 6/7 9.4E+1 to

1.9E+2 * * *


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Table 4.20: Lobster, Edible, Cooked Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 7 2.6E+1 9.8E+0 to 6.1E+1 8.2E+1 6/7 6.3E+1 to

1.0E+2 * * *

* There are no reference samples.

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Table 4.21: Periwinkles, Edible, Raw Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 16 8.9E+1 3.2E+1 to 1.5E+2 2.1E+2 4/16 1.1E+2 to

3.2E+2 * * *


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Table 4.22: Aquaculture Salmon, Raw Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 2 3.6E+1 6.1E+0 to 6.5E+1 1.1E+2 2/2 9.4E+1 to

1.3E+2 * * *


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Table 4.23: Scallops, Raw Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 5 3.4E+1 1.1E+1 to 7.3E+1 1.6E+2 5/5 1.3E+2 to

2.1E+2 * * *


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Table 4.24: Sea Plants, Wet Mass (Bq·kg-1)

Analysis Type

Total Number



K-40 12 2.3E+1 3.2E+0 to 8.5E+1 3.0E+2 12/12 2.3E+2 to

5.2E+2 * * *


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4.20 Sediment Of the 39 samples analysed, Be-7 was detected in seven, Ac-228 in 19 and K-40 in 35 samples. None of these results are attributable to the operation of PLNGS. Sediments are collected quarterly from ten locations shown in Figure 3.05. The finer grains are analysed by selective sieving of the material. Thirty-five samples contained K-40 (3.5E+02 to 7.0E+02 Bq·kg-1) from the natural potassium in feldspar, a common mineral. Seven samples contained cosmogenically produced Be-7 (1.8E+01 to 4.4E+01 Bq·kg-1). Nineteen samples contained Ac-228 (4.8E+00 to 2.9E+01 Bq·kg-1), a radioactive progeny of naturally occurring Th-232. Sediment samples analysed between 1977 and 1982, before PLNGS began operations, contained an average Cs-137 concentration of 5.0E+00 Bq·kg-1. A small additional Cs-137 component was added to this reservoir from Chernobyl in 1986 and from Fukushima in 2011. Finer grain sediments have a higher natural radioactivity content than coarse sediments. Table 4.25 is a summary of the detected radionuclides in sediment. Figure 4.19 shows individual Cs-137 results. “Less Than” values are plotted for non-detected results.

Figure 4.19: Cesium-137 (Sediment)

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Table 4.25: Sediment (Bq·kg-1)

Analysis Type

Total Number



Be-7 39 1.3E+1 7.6E+0 to 3.0E+1 3.3E+1 5/35 1.8E+1 to

4.4E+1 3.7E+1 2/4 3.6E+1 to 3.7E+1

Ac-228 39 4.2E+0 1.9E+0 to 2.0E+1 2.0E+1 17/35 4.8E+0 to

2.9E+1 2.7E+1 2/4 2.5E+1 to 2.8E+1

K-40 39 2.5E+1 4.2E+0 to 1.4E+2 5.6E+2 31/35 4.6E+2 to

7.0E+2 4.5E+2 4/4 3.5E+2 to 5.1E+2

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4.21 Ambient Gamma Measurements of Intertidal Zone (Ion Chamber) Environmental gamma survey measurements are made in the intertidal zone on beaches in the Lepreau area and at the reference location 28 km to the east-northeast (Figure 3.05). Although TLDs are preferred in measuring such exposures since they span the entire year and provide integrated measurements, they cannot be used in these locations. Instead, beach surveys are performed and grab samples of sediments are analysed. Radiation values measured in 2016 were consistent with those measured prior to station start-up in 1982. These values are summarised in Table 4.26.

Table 4.26: Ambient Gamma Measurements of Intertidal Zone (Ion Chamber) – (μSv·h-1)

Location 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

B01 0.11 0.18 0.15 0.20 B02 0.16 0.19 0.18 0.13 C01 0.13 0.18 0.15 0.11 D04 0.17 0.10 0.11 0.13 E03 0.14 0.09 0.16 0.16 G01 0.12 0.15 0.13 0.18 H03 0.14 0.08 0.11 0.17 N04 0.17 0.01 0.18 0.21 P02 0.12 0.14 0.12 0.09

Q01R 0.16 0.14 0.19 0.15

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4.22 LEM Composite Water (Sr-89,90) When Sr-89,90 emissions are low, the expected concentration of Sr-89,90 in seawater is below the detection limit. The LEM collects samples of PLNGS liquid emissions at their source. A monthly composite is sent to the lab for analysis. Fourteen of these composites were analysed for Sr-89,90. If the monthly emissions are more than one percent of the monthly DRL, a Sr-89,90 analysis is performed on seawater. Since the emissions in 2016 were 1E-09% DRL (and in no month exceeded one percent of the monthly DRL) for Sr-90, and Sr-89 was not detected, no further analyses were required. Figure 4.20 shows the Sr-90 emissions from PLNGS.

Note: The Monthly DRL for Sr-90 is 5.0E+14 Bq

Figure 4.20: Liquid Sr-90 Emissions

4.23 Bore Hole Water, SRWMF Of the 100 samples analysed, low levels of H-3 were detected in 95, Be-7 in four and K-40 in two. The H-3 results are attributable to the operation of PLNGS. Samples are taken three times per year from 35 drilled wells. Occasionally, a well is dry or inaccessible and no sample is available. Tritium concentrations averaged 1.5E+02 Bq·L-1 (3.6E+01 to 3.8E+02 Bq·L-1) near the Phase 1 facility, 4.8E+01 Bq·L-1 (1.4E+01 to 3.3E+02 Bq·L-1) near the Phase 2 facility and 1.1E+02 Bq·L-1 (1.4E+01 to 3.9E+02 Bq·L-1) near the Phase 3 facility. Tritium washes out into precipitation and subsequently drains into some of the bore holes. Precipitation analyses (Section 4.14) indicate H-3 concentrations ranging from 1.5E+01 to 4.1E+02 Bq·L-1 in 21 of 25 samples.

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Four samples contained cosmogenically produced Be-7 (4.7E+00 to 1.3E+01 Bq·L-1). Naturally occurring K-40 was detected in two samples (4.3E+00 to 7.5E+00 Bq·L-1). Results are presented in Tables 4.27 to 4.29. Figure 4.21 shows the H-3 activity at each bore hole for each sample. Locations I10A-I10F are the closest to the onsite SRWMF- Phase 1 structures and may be affected by the elevated H-3 levels associated with the structures. “Less Than” values are plotted for non-detected results.

Figure 4.21: Tritium (Bore Hole Water, SRWMF)

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Table 4.27: Bore Hole Water, SRWMF - Phase 1 (Bq·L-1)

Analysis Type

Total Number



H-3 15 1.3E+1 1.2E+1 to 1.3E+1 1.5E+2 15/15 3.6E+1 to

3.8E+2 * * *


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Analysis Type

Total Number



H-3 54 1.2E+1 1.1E+1 to 1.4E+1 4.8E+1 51/54 1.4E+1 to

3.3E+2 * * *

Be-7 54 1.6E+0 8.8E-1 to 2.8E+0 7.9E+0 4/54 4.7E+0 to

1.3E+1 * * *

K-40 54 3.3E+0 1.1E+0 to 7.8E+0 5.9E+0 2/54 4.3E+0 to

7.5E+0 * * *


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76

Analysis Type

Total Number



H-3 31 1.3E+1 1.2E+1 to 1.4E+1 1.1E+2 29/31 1.4E+1 to

3.9E+2 * * *


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4.24 Parshall Flume Water, SRWMF Of the 156 samples analysed, H-3 was detected in 131. These results are attributable to the emissions from PLNGS and the material stored in the Phase 1 structures. Rainwater and snow melt at the SRWMF (Phases 1, 2 and 3) are obtained from drainage channels (flumes) constructed to collect surface runoff from these areas. Samples are collected and analysed on a weekly basis. There is little or no flow into or out of these collection locations during the winter months and values for H-3 tend to vary little from one week to the next except after heavy rain. The average H-3 value for each phase is:

• 2.5E+02 Bq·L-1 at Phase 1 • 1.0E+02 Bq·L-1 at Phase 2 • 1.2E+02 Bq·L-1 at Phase 3.

The Phase 1 results are higher than Phases 2 and 3 due to H-3 vapour escaping from the structures and condensing onto surfaces. Tables 4.30 to 4.32 are summaries of the detected radionuclides in the flumes. Figure 4.22 compares the H-3 in the samples from the three facilities. “Less Than” values are plotted for non-detected results. Naturally occurring K-40 was detected in two Phase 3 samples (2.2E+00 to 3.2E+00 Bq·L-1).

Figure 4.22: Tritium (Parshall Flume Water, SRWMF)

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Table 4.30: Parshall Flume Water, SRWMF - Phase 1 (Bq·L-1)

Analysis Type

Total Number



H-3 52 1.3E+1 1.2E+1 to 1.4E+1 2.5E+2 52/52 3.8E+1 to

8.8E+2 * * *


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Analysis Type

Total Number



H-3 52 1.3E+1 1.2E+1 to 1.4E+1 1.0E+2 41/52 1.5E+1 to

5.7E+2 * * *


of 152



Analysis Type

Total Number



H-3 52 1.3E+1 1.2E+1 to 1.4E+1 1.2E+2 38/52 1.4E+1 to

6.9E+2 * * *

K-40 52 3.1E+0 1.6E+0 to 7.2E+0 2.7E+0 2/52 2.2E+0 to

3.2E+0 * * *


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4.25 Hemlock Knoll Regional Sanitary Landfill Program PLNGS disposes of its non-active waste at the public landfill facility at Hemlock Knoll. The monitoring program consists of dosimeter placement at key locations. There were 16 TLD results from Hemlock Knoll in 2016. TLD results appear in Table 4.06 (location codes YTL1 to YTL4). 4.26 Meteorological Data The meteorological data for 2016 were collected at ten minutes intervals and are presented in Table 4.33. Wind Rose data for 2016 are presented in Figure 4.23.

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Table 4.33: Meteorological Data for Point Lepreau (2016)

Temperature

(Degrees Celsius) 10 Metre Tower Data

Wind Direction* (Relative %)

42 Metre Tower Data

Mean Daily Extreme % Observations from

Month Avg Max Min Max Min N NE E SE S SW W NW

January -2.8 0.7 -6.7 11.3 -17.8 37 6 1 4 4 17 20 10

February -1.9 2.5 -6.6 11.6 -19.3 13 4 8 12 11 13 22 16

March -0.2 3.5 -3.8 10.2 -15.3 19 12 3 9 10 11 22 15

April 4.1 8.4 -0.4 21.1 -9.9 13 8 6 16 11 10 19 16

May 9.0 13.3 6.1 20.7 0.6 21 16 5 14 13 17 8 6

June 12.7 16.8 9.4 22.2 5.0 6 12 9 19 17 16 13 7

July 16.1 20.4 13.1 26.9 11.3 12 13 6 18 20 20 7 5

August 17.2 21.6 14.3 26.1 11.6 11 14 4 19 21 13 13 6

September 15.0 18.9 11.7 24.9 4.4 14 8 6 19 17 11 13 12

October 10.5 13.9 6.9 21.2 1.1 15 12 4 14 14 15 12 15

November 5.7 8.7 3.1 13.5 -2.7 19 13 4 7 12 15 18 12

December -2.2 2.2 -6.6 11.5 -21.1 7 8 3 6 6 19 32 19

Average for 2016 7.0 Max Min Extreme

Max Extreme

Min 16 10 5 13 13 15 17 11 10.9 3.4 26.9 -21.1

*Each compass direction covers ±22.5 degrees.

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Figure 4.23: Wind Rose for Point Lepreau (2016)

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5 Trends (REMP) The following trends were observed in the historical data:

• Gaseous tritium and C-14 emissions remained low in 2016. • Tritium continues to be detected in air and water samples (higher onsite than offsite). • There continues to be a difference between onsite and offsite thermoluminescent dosimeter

(TLD) measurements (elevated onsite compared with offsite). • The radionuclide concentration in most sample types continues to remain at preoperational

(background) levels due to the history of low emissions. As in the figures in Section 4, “Less Than” values are plotted for non-detected values. All location codes are described in Appendix C. 5.01 Dose from Airborne and Liquid Pathways Radiation dose from PLNGS emissions continues to be well below the public dose limit (1000 microsieverts per annum), and also well below the design and operating target for PLNGS (50 microsieverts per annum). See Figure 5.01.

Figure 5.01: Dose from Airborne and Liquid Pathways

5.02 Tritium (Water Vapour) Station airborne tritium emissions are shown in Figure 5.02). Figure 5.04 shows the airborne H-3 concentration at the onsite stations and the offsite locations are shown in Figure 5.03. The differences are due to increasing dilution with distance from the emissions stack.

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Note: The current Annual DRL for H-3 is 2.8E+17 Bq

Figure 5.02: Airborne H-3 Emissions

Figure 5.03: Tritium (Water Vapour) at Offsite Air Stations

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Figure 5.04: Tritium (Water Vapour) at Onsite Air Stations

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5.03 Cesium-137 (Soil) Cesium-137 from the fallout of past atmospheric weapons tests and international events tends to accumulate in the organic layer of soil. There can be large fluctuations in Cs-137 levels due to this organic load in the sample. The value plotted for each year in Figure 5.05 is the mean of all values for that year. “Less Than” values are plotted for non-detected values.

Figure 5.05: Cesium-137 (Soil)

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5.04 Tritium (Monitoring Well Water, Near Plant) The concentration of H-3 in the monitoring wells are shown in Figure 5.06.

Figure 5.06: Tritium (Monitoring Well Water, Near Plant)

5.05 Tritium and C-14 (Seawater) Tritium emissions to seawater have been declining since start up activities after the refurbishment outage in 2012 (Figure 5.07). The increase in 2012 was due to restart activities. The value plotted for each year in Figure 5.07 is the mean of all values for that year. “Less Than” values are plotted for non-detected values. Carbon-14 emissions were up in 2012 due to restart activities including the transfer of moderator water to the calandria. The expected concentration of C-14 in seawater is below the detection limit (Figure 5.08).

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Note: The current Annual DRL for H-3 is 4.6E+19 Bq

Figure 5.07: Liquid H-3 Emissions

Note: The current Annual DRL for C-14 is 3.3E+14 Bq

Figure 5.08: Liquid C-14 Emissions

5.06 Strontium-90 (LEM Water) The maximum values for Sr-90 still represent only a small fraction of the DRL and are due to activity just above the detection limit (Figure 5.09).

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Note: The current Annual DRL for Sr-90 is 6.0E+15 Bq

Figure 5.09: Liquid Sr-90 Emissions

5.07 Tritium (Parshall Flume Water) The H-3 values at Phase 2 and Phase 3 are typically less than those at Phase 1. The Phase 1 results are due to H-3 vapour escaping from the structures and condensing onto surfaces (Figure 5.10).

Figure 5.10: Tritium (Parshall Flume Water)

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6 Dose Estimation The DRLs apply to the release point for each of the two major effluent pathways for PLNGS: the ventilation stack for airborne releases; and, for liquid releases, the discharge point of the Condenser Cooling Water (CCW) duct into the Bay of Fundy. The releases are assumed to be continuous. All relevant exposure routes to the public are factored into the DRL calculations. Crossover routes between the two pathways are insignificant, and therefore they are not considered. The DRL document identifies the Representative Person associated with radioactive airborne and liquid effluent releases from the PLNGS, and documents the magnitude of activity of each nuclide released through either pathway in one calendar year that would cause the Representative Person to receive or be committed to the regulatory dose limit for a member of the public. This activity is called the derived release limit (DRL) for that nuclide. Dose estimates to members of the local communities that are based on the DRLs are conservative CSA Standard N288.1-08, Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities, which forms the basis for DRLs, includes conservative values for food intake and other parameters. In some cases, even more conservative site-specific data are used. The detailed discussion of these pathways may be found in RD-01364-L1, Derived Release Limits for Radionuclides in Airborne and Liquid Effluents. The airborne exposure pathways from PLNGS to the public are:

• internal from inhalation • external from immersion in a plume • external from contaminated ground (ground shine) • internal from ingestion of contaminated well water • external from immersion in contaminated well water • internal from ingestion of contaminated soil, plants and animals.

The selection of Representative Person is based upon which local residential areas receive the greatest exposure from airborne releases, and the potential of intakes based upon dietary and behavioral habits. Welch Cove was selected as the location for the representative group for all airborne releases. Welch Cove is a small community of approximately 32 residences along a two kilometre stretch of road that extends from northwest to north-northwest of PLNGS. A hypothetical family consisting of two adults, a ten year old child and a one year old infant is considered to be representative of the community. The liquid exposure pathways from PLNGS to the public are:

• external from diving in contaminated water • external from exposure to contaminated sediment (while harvesting clams and dulse) • internal from ingestion of contaminated fish, lobster, clams, and dulse. • external from diving for sea urchins

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The selection of a Representative Person is based upon dietary and behavioral habits of local residents. A representative family of two adults, a ten-year-old child and a one-year-old infant was selected. The DRLs are based on CSA Standard N288.1-08, Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities. Station releases of a radionuclide at 100% DRL for a year would result in a dose to the Representative Person of 1000 μSv. In 2016 (Table 6.01), the liquid releases were 7.2E-3% DRL, which corresponds to 0.07 μSv to the Representative Person. Airborne releases for 2016 were 8.5E-2% DRL, which corresponds to a public dose of 0.85 μSv. Adjustments are made to the DRL based on operational considerations or emission location. For example, a reduced CCW flow changes the dilution factor which decreases the DRL. As shown in Table 6.02 and Figures 6.01 and 6.02, H-3 accounts for 64.5% of the dose from airborne emissions, and 15.8% of the dose from liquid emissions in 2016. The other major contributor to dose from airborne emissions was Argon-41 (32.0%). The other major contributors to dose from liquid emissions were Zr-95 (45.0%), C-14 (14.8%), Co-60 (12.8%) and Nb-95 (8.7%) Because of the protective assumptions used in the DRL calculations, and the relatively low level of emissions, the most exposed member of the general public received less than the calculated dose of 0.92 μSv. This radiation dose may be compared with the individual natural radiation dose in the Lepreau area of approximately 2000 to 3000 μSv per annum. (TLDs show only the external, penetrating component, amounting to about 500 to 1000 μSv.) This includes natural dose contributions from ground, air, food and from an assumed low concentration of radon in homes. A significant fraction of Canadian homes contain radon levels that give a much larger radiation dose than the 2000 to 3000 μSv.

Table 6.01: Annual Dose (2016)

Source of Dose to the Representative Person

Dose to the Representative Person (μSv.a-1)

PLNGS airborne emissions 0.85 PLNGS liquid emissions 0.07

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Table 6.02: Contribution of Radionuclides to Dose in Each Pathway (2015)

Radiouclide Contribution to Dose

(from Airborne Emissions)

Contribution to Dose (from Liquid Emissions)

H-3 64.5 % 15.8 % C-14 2.0 % 14.8 % Ar-41 32.0 % ---- Co-60 ---- 12.8 % Nb-95 ---- 8.7 % Zr-95 ---- 45.0 %

All others 1.4 % 2.9 % TOTAL 100 % 100 %

Note: Only radionuclides contributing 0.5% or more are itemized.

Figure 6.01: Contribution of Radionuclide to Total Dose (Airborne Pathway)-

2016

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Figure 6.02: Contribution of Radionuclide to Total Dose (Liquid Pathway) –

2016

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7 Quality Assurance Results (REMP) The purpose of Quality Assurance is to provide confidence in the program and demonstrate that the program is able to meet its objectives. QA is a system whereby the laboratory can assure the regulator and NB Power that the laboratory is generating accurate and reproducible data. It encompasses:

• personnel • procedures • measurements • sample integrity • records • annual review • program audits • program improvement

This section describes how QA was achieved for the year 2016. The specific procedures can be found in HPF-03541-EN04, Quality Assurance of the Environmental Program. 7.01 Quality Control Checks The six main pieces of analytical equipment used in the OERMP have a quality control (QC) check performed at the start of each working day. A background count is made each weekend to ensure the absence of contamination in the gamma spectrometer sample chamber. Key instrument parameters are checked and the results are compared against tolerance limits, and are also compared with previous results to detect trends in performance. This ensures that the parameters are consistent and remain free from significant drift or random variation that could influence the analyses. A compilation of the results and statistical fluctuations is maintained, and from these data the upper and lower flag limits are determined. If any equipment exceeds these limits, it is not used for analytical work until the problem has been resolved. To perform the quality control checks, radiation sources traceable to US or Canadian standards (National Institute of Standards and Technology and National Research Council) are used. The QC evaluations in the laboratory cover the following instruments:

1. Canberra Intrinsic Ge Gamma Spectrometer 2. Beckman LS 6000TA Liquid Scintillation Counter 3. Tennelec LB-5100 Gross Alpha/Beta Counter 4. Protean WPC 9550 Alpha/Beta Counter 5. Panasonic UD-716AGL TLD Reader 6. Panasonic UD-7900 TLD Reader

Throughout the year there were some results outside expectations for each of the instruments (Table 7.01). Most of these failures involved only one of the six to ten parameters monitored for each system. All of these failures were resolved before analytical work resumed.

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Table 7.01: QC Passes & Failures

Instrument

Number of Parameters Monitored Per Check

Number of

Checks

Number of Individual Parameters

Tested

Number of Individual Parameters

Failed Canberra Intrinsic Ge Gamma Spectrometer 6 288 1728 73

Canberra Intrinsic Ge Gamma Spectrometer (Weekend Long Background)

8 56 448 0

Beckman LS 6000TA Liquid Scintillation Counter 10 285 2850 81

Tennelec LB-5100 Gross Alpha/Beta Counter 8 244 1952 9

Protean WPC 9550 Alpha/Beta Counter 8 242 1936 25

Panasonic UD-716AGL TLD Reader 8 221 1768 10

Panasonic UD-7900 TLD Reader 8 208 1664 9

7.01.01 Intrinsic Ge Gamma Spectrometer

A daily check of seven system parameters is performed for the germanium gamma spectroscopy system. Measurements are made of the energy centroids, full width half maxima (FWHM) and efficiencies of two widely separated photon energies of Eu-152. These show the accuracy and precision of the system relative to the defined limits of acceptance. The rate of liquid nitrogen consumption is monitored to verify the physical integrity of the cryostat (this parameter is not reflected in the numbers in Table 7.01). A computer program processes the results to generate QC plots and performs statistical tests to detect out-of-range values. A 200 000 s background count is made each weekend to ensure the absence of contamination in the sample chamber. The QC program evaluates the total counts in eight separate regions of the background spectrum, and out-of-range values are flagged for assessment. The efficiency calibration of the gamma spectroscopy system is checked annually for each of the counting geometries. This is accomplished using calibration standards derived from a mixed nuclide standard traceable to the U.S. National Institute of Standards and Technology (NIST). 7.01.02 Beckman LS 6000TA Liquid Scintillation Counter

A set of sealed tritium, C-14 and background standards traceable to NIST is analysed daily. Statistical parameters must lie within defined limits or the equipment will not be used. These same standards are used to calibrate the instrument for each analysis run.

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7.01.03 Tennelec LB-5100 Gross Alpha/Beta Counter Planchet standards of Am-241 and Sr-Y-90 are analysed daily. Alpha and Beta discrimination allows the simultaneous analysis of alpha and beta emissions on all samples analysed. Planchet and filter backgrounds are included in the QC checks. These same standards are used to calibrate the instrument for each analysis run. 7.01.04 Protean WPC 9550 Alpha/Beta Counter Planchet standards of Am-241, Tc-99 and Sr-Y-90 are analysed daily. Alpha and Beta discrimination allows the simultaneous analysis of alpha and beta emissions on all samples analysed. Planchet backgrounds are included in the QC checks. The Tennelec standards are used to calibrate the instrument for each analysis run. 7.01.05 Panasonic UD-716AGL and UD-7900U TLD Readers In each of the two TLD readers, a set of 16 TLDs is exposed in the Panarad Irradiator and read out in the TLD reader. The mean of each of the four elements, dark current, reference light, reference element, and lamp flashes must all be within specified limits. The QA aspect of this system is covered in detail in the TLD procedures:

• HPF-03541-TL03, Performing a Quality Control Check on Panasonic Automatic TLD Readers.

• HPF-03541-TL09, Performing Quality Assurance Testing of the Dosimetry System.

• HPF-03541-TL13, Processing Internal Quality Assurance Test Data.

7.01.06 Other Instruments Other instruments (balances, pipettors) are checked or calibrated at least annually. See HPF-03541-EN05, Calibration, Maintenance and Repair of Equipment Used for the Environmental Program,. Frequencies of calibration are based on reproducibility of measurements and on time stability tests to ensure that the measurements are within the specified tolerances for accuracy. The gamma survey and contamination meters are calibrated at PLNGS on an annual basis. 7.02 External QA The external quality assurance program consists of inter-comparisons with other laboratories to give independent verification of analytical performance. The frequency of each program may vary at the discretion of the sponsoring agency (see Table 7.03). Four such groups – Kinectrics, Eckert & Ziegler Analytics, Environmental Resource Associates (ERA) and the National Research Council (NRC) - provide five percent of the sample load in the laboratory with blind samples. Results of our performance with these samples give an indication of the quality of measurements the laboratory is capable of producing.

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The same results are tabulated by medium in Tables 7.04 to 7.11. The QA agent defines acceptable performance, generally in terms of an expected range. A results outside expectations signals the need to assess the procedures, analytical methods, or equipment calibrations. There were 40 results that were outside expectations out of 253 nuclide comparisons on 57 samples in the external QA program. The reasons are given in Table 7.02.

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Table 7.02: External Quality Assurance Results Outside Expected Range

Medium Nuclide Number Reason

Filter

Beta 6 Under investigation. PICA raised. Cs-134 2 Suspected detector stability problem. Corrected. Sr -89 1 Under investigation. PICA raised. Sr -90 1 Under investigation. PICA raised.

Charcoal Cartridge I-131 1 Operator error. PICA raised.

Water

Alpha 1 Under investigation. PICA raised.

Beta 3 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Am-241 2 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

C-14 2 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Cd-109 2 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Ce-139 1 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Co-57 1 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Cs-137 1 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Co-60 2 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Hg-203 1 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Sn-113 1 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Sr-85 2 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Sr-89 4 Under investigation. PICA raised. Sr-90 1 Under investigation. PICA raised.

Y-88 2 Pass/Fail limits of ±10% compared to all others who use ±3s. At +15% this would be a pass.

Food Cs-134 1 Suspected detector stability problem. Corrected. Cs-137 1 Suspected detector stability problem. Corrected. Zn-65 1 Suspected detector stability problem. Corrected.

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Table 7.03: External Quality Assurance Frequency

Media Analyses Number of QA Samples External Agencies

Filters

Gross Alpha/Beta

2 ERA

2 Eckert & Ziegler Analytics

4 (2 gross beta only, 2 gross alpha only) Kinectrics

Gamma 2 ERA


Sr-89,90

2 (only Sr-90, on gamma sample) ERA


Charcoal Cartridges Gamma 4 Eckert & Ziegler

Analytics Environmental

Gamma TLD 5 NRC

Milk Gamma 4 Eckert & Ziegler Analytics

Water

Gross Alpha/Beta

2 ERA


2 (gross beta only) Kinectrics

H-3 4 Kinectrics C-14 4 Kinectrics

Gamma 2 Kinectrics


Sr-89,90 4 (on gamma sample) Eckert & Ziegler Analytics

Food/Vegetation Gamma 2 ERA


Soil/Sediment Gamma 2 ERA


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Table 7.04: Filter Performance (External QA)

Analysis QA Agent (pCi·filter-1 ± 2 sigma)

NB Power (pCi·filter-1 ± 2 sigma)

NB Power/ QA Agent (ratio)

ALPHA

2.28 ± 0.07 2.37 ± 0.14 1.04 4.29 ± 0.14 4.66 ± 0.24 1.09 5.03 ± 0.67 5.28 ± 0.06 1.05 5.03 ± 0.67 5.47 ± 0.06 1.09 2.59 ± 1.05 2.85 ± 0.05 1.10 2.63 ± 1.07 2.83 ± 0.05 1.08

BETA

7.62 ± 0.25 10.9 ± 0.5 1.43 Fail 8.58 ± 0.28 13.2 ± 0.6 1.53 Fail 14.1 ± 1.9 20.7 ± 0.2 1.47 Fail 18.4 ± 2.5 26.7 ± 0.2 1.45 Fail 2.01 ± 0.55 2.96 ± 0.04 1.47 Fail 2.23 ± 0.61 3.85 ± 0.05 1.72 Fail

Am-241 1.70 ± 0.42 1.86 ± 0.29 1.09 1.57 ± 0.38 1.33 ± 0.29 0.85

Ce-141 4.22 ± 0.14 4.00 ± 0.26 0.95 3.92 ± 0.13 4.14 ± 0.27 1.06

Co-58 4.29 ± 0.14 4.11 ± 0.31 0.96 4.00 ± 0.13 4.22 ± 0.32 1.06

Co-60

5.22 ± 0.17 5.29 ± 0.28 1.01 4.88 ± 0.16 5.03 ± 0.28 1.03 23.1 ± 3.7 19.9 ± 0.9 0.87 33.3 ± 5.2 29.7 ± 1.3 0.89

Cr-51 8.36 ± 0.27 7.88 ± 0.78 0.94 7.66 ± 0.25 8.95 ± 0.87 1.17

Cs-134

5.29 ± 0.17 4.44 ± 0.45 0.84 4.88 ± 0.16 4.03 ± 0.45 0.83 11.2 ± 2.3 6.62 ± 0.72 0.59 Fail 22.7 ± 4.6 14.1 ± 1.1 0.62 Fail

Cs-137

3.65 ± 0.12 3.40 ± 0.26 0.93 3.46 ± 0.11 3.62 ± 0.28 1.05 42.6 ± 8.0 35.0 ± 2.0 0.82 43.3 ± 8.2 34.6 ± 2.0 0.80

Fe-59 3.69 ± 0.12 4.26 ± 0.48 1.15 3.42 ± 0.11 4.03 ± 0.47 1.18

Mn-54 3.81 ± 0.12 3.96 ± 0.30 1.04 3.54 ± 0.12 3.77 ± 0.30 1.07

Sr-89

3.05 ± 0.12 2.80 ± 0.23 0.92 3.22 ± 0.11 3.92 ± 0.31 1.22 3.18 ± 0.10 3.17 ± 0.34 1.00 3.52 ± 0.12 7.18 ± 0.53 2.04 Fail

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Table 7.05 (continued): Filter Performance (External QA)

Analysis QA Agent (pCi·filter-1 ± 2 sigma)

NB Power (pCi·filter-1 ± 2 sigma)


Sr-90

0.400 ± 0.013 0.247 ± 0.039 0.62 Fail 0.525 ± 0.017 0.666 ± 0.075 1.27 0.481 ± 0.016 0.622 ± 0.110 1.29 0.477 ± 0.016 0.522 ± 0.067 1.09 5.55 ± 1.87 6.07 ± 0.40 1.09 3.74 ± 1.25 4.66 ± 0.24 1.25

Zn-65

7.14 ± 0.23 7.88 ± 0.64 1.10 6.66 ± 0.22 7.59 ± 0.61 1.14 13.2 ± 2.9 12.9 ± 1.0 0.98 42.6 ± 9.4 41.1 ± 2.5 0.97

Table 7.06: Charcoal Cartridge Performance (External QA)

Analysis QA Agent

(pCi·cartridge-1 ± 2 sigma)

NB Power (pCi·cartridge-1

± 2 sigma)

NB Power/QA Agent (ratio)

I-131

3.46 ± 0.11 3.08 ± 0.37 0.89 3.30 ± 0.11 3.33 ± 0.28 1.01 2.21 ± 0.07 5.03 ± 0.53 2.28 Fail 3.63 ± 0.12 3.17 ± 0.30 0.87

Table 7.07: Milk Performance (External QA)

Analysis QA Agent (pCi·L-1 ± 2 sigma)

NB Power (pCi·L-1 ± 2 sigma)


Ce-141

3.64 ± 0.12 3.66 ± 0.29 1.01 5.14 ± 0.17 5.18 ± 0.38 1.01 3.45 ± 0.11 3.21 ± 0.25 0.93 5.29 ± 0.17 5.40 ± 0.40 1.02

Co-58

4.33 ± 0.14 4.07 ± 0.33 0.94 5.25 ± 0.17 5.03 ± 0.38 0.96 3.60 ± 0.12 3.52 ± 0.28 0.98 5.40 ± 0.18 5.40 ± 0.41 1.00

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Table 7.07 (continued): Milk Performance (External QA)

Analysis QA Agent (pCi·L-1 ± 2 sigma)



Co-60

9.03 ± 0.30 9.66 ± 0.52 1.07 6.40 ± 0.21 6.51 ± 0.37 1.02 5.00 ± 0.16 5.33 ± 0.30 1.07 6.59 ± 0.22 6.99 ± 0.39 1.06

Cr-51

8.99 ± 0.29 9.07 ± 1.08 1.01 10.2 ± 0.3 9.47 ± 1.02 0.93 8.73 ± 0.29 7.29 ± 0.84 0.83 10.4 ± 0.3 10.2 ± 1.1 0.99

Cs-134

4.81 ± 0.16 4.77 ± 0.42 0.99 6.44 ± 0.21 5.70 ± 0.62 0.89 5.03 ± 0.16 4.63 ± 0.57 0.92 6.59 ± 0.22 6.29 ± 0.62 0.96

Cs-137

5.96 ± 0.20 6.07 ± 0.45 1.02 4.44 ± 0.15 4.18 ± 0.32 0.94 4.40 ± 0.14 4.40 ± 0.33 1.00 4.66 ± 0.15 4.77 ± 0.36 1.02

Fe-59

4.85 ± 0.16 5.14 ± 0.52 1.06 4.51 ± 0.15 4.59 ± 0.46 1.02 3.35 ± 0.11 3.64 ± 0.39 1.09 4.63 ± 0.15 5.11 ± 0.49 1.10

I-131

3.04 ± 0.10 2.95 ± 0.46 0.97 3.50 ± 0.11 3.42 ± 0.32 0.98 2.66 ± 0.09 2.52 ± 0.24 0.95 3.60 ± 0.12 3.58 ± 0.36 0.99

Mn-54

4.33 ± 0.14 4.07 ± 0.33 0.94 4.63 ± 0.15 4.70 ± 0.36 1.02 5.62 ± 0.18 5.77 ± 0.43 1.03 4.77 ± 0.16 5.03 ± 0.38 1.05

Zn-65

6.62 ± 0.22 6.92 ± 0.57 1.04 8.70 ± 0.29 9.21 ± 0.73 1.06 6.62 ± 0.22 7.07 ± 0.58 1.07 9.03 ± 0.30 9.77 ± 0.77 1.08

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Table 7.08: Water Performance (External QA)

Analysis

QA Agent (pCi·L-1 ± 2 sigma) or

(pCi·kg-1 ± 2 sigma)

NB Power (pCi·L-1 ± 2 sigma) or

(pCi·kg-1 ± 2 sigma)


ALPHA

2.77 ± 0.09 3.40 ± 0.30 1.23 5.40 ± 0.18 5.74 ± 0.48 1.06 4.33 ± 1.72 7.29 ± 0.28 1.68 fail 6.11 ± 2.43 8.29 ± 0.28 1.36

BETA

9.25 ± 0.30 12.4 ± 0.8 1.34 Fail 10.8 ± 0.4 14.5 ± 1.0 1.33 Fail 13.0 ± 1.7 16.5 ± 0.2 1.28 Fail 2.79 ± 0.85 3.24 ± 0.10 1.16 4.81 ± 1.46 6.33 ± 0.14 1.32

Am-241 85100 ± 5600 107000 ± 6000 1.26 Fail 102000 ± 7000 114000 ± 7000 1.12 Fail

C-14

1110 ± 70 481 ± 17 0.43 Fail 185000 ± 12000 135000 ± 1000 0.73 Fail 37000 ± 2500 35200 ± 200 0.95

518000 ± 33000 474000 ± 3000 0.91

Cd-109 1.1E+6 ± 7.6E+4 1.5E+6 ±

8.4E+4 1.32 Fail

1.3E+6 ± 8.9E+4 1.6E+6 ± 9.3E+4 1.18 Fail

Ce-139 38500 ± 2500 46600 ± 3000 1.21 Fail 47400 ± 3100 49600 ± 2800 1.05

Ce-141

4.37 ± 0.14 4.77 ± 0.60 1.09 5.44 ± 0.18 5.59 ± 0.61 1.03 3.15 ± 0.10 3.07 ± 0.42 0.97 5.11 ± 0.17 5.03 ± 0.56 0.99

Co-57 27800 ± 1900 34500 ± 1500 1.24 Fail 31500 ± 2200 34000 ± 1400 1.08

Co-58

5.22 ± 0.17 5.29 ± 0.67 1.01 5.59 ± 0.18 5.62 ± 0.68 1.01 3.29 ± 0.11 3.28 ± 0.48 1.00 5.25 ± 0.17 5.44 ± 0.67 1.04

Co-60

10.8 ± 0.4 11.4 ± 0.9 1.05 6.77 ± 0.22 6.96 ± 0.63 1.03 4.55 ± 0.15 4.92 ± 0.51 1.08 6.36 ± 0.21 6.73 ± 0.62 1.06

51800 ± 3500 67700 ± 2800 1.31 Fail 63600 ± 4200 72200 ± 2900 1.13 Fail

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Table 7.08 (continued): Water Performance (External QA)

Analysis

QA Agent (pCi·L-1 ± 2 sigma)

or (pCi·kg-1 ± 2 sigma)




Cs-134

5.81 ± 0.19 6.07 ± 0.71 1.04 6.85 ± 0.22 6.48 ± 0.71 0.95 4.59 ± 0.15 4.48 ± 0.60 0.98 6.40 ± 0.21 6.92 ± 0.78 1.08

Cs-137

7.18 ± 0.23 7.22 ± 0.79 1.01 4.74 ± 0.15 4.66 ± 0.59 0.98 4.00 ± 0.13 3.77 ± 0.52 0.94 4.51 ± 0.15 4.59 ± 0.59 1.02

32900 ± 2200 41400 ± 2400 1.26 Fail 40300 ± 2700 44000 ± 2500 1.09

Fe-59

5.81 ± 0.19 7.07 ± 1.42 1.22 4.77 ± 0.16 5.11 ± 1.04 1.07 3.06 ± 0.10 3.54 ± 0.90 1.15 4.48 ± 0.15 5.14 ± 1.04 1.15

H-3

1.3E+6 ± 8.6E+4 1.3E+6 ± 7.0E+4 0.99 3.0E+6 ± 2.0E+5 2.9E+6 ± 1.6E+4 0.97 114000 ± 7000 111000 ± 1000 0.97

1.1E+6 ± 7.4E+4 1.1E+6 ± 6.1E+3 0.99

Hg-203

93600 ± 6100 112000 ± 8000 1.20 Fail 104000 ± 7000 108000 ± 8000 1.04

3.58 ± 0.12 3.57 ± 0.52 1.00 1.81 ± 0.06 1.58 ± 0.34 0.87

Mn-54

3.40 ± 0.11 3.23 ± 0.48 0.95 5.18 ± 0.17 6.36 ± 0.74 1.23 4.92 ± 0.16 5.40 ± 0.66 1.10 5.14 ± 0.17 5.22 ± 0.64 1.01

Sn-113 4.63 ± 0.15 5.44 ± 0.67 1.18 67300 ± 4400 84000 ± 4800 1.25 Fail

Sr-85 81800 ± 5400 103000 ± 6000 1.26 Fail 95100 ± 6300 107000 ± 6000 1.12 Fail

Sr-89

3.44 ± 0.11 4.63 ± 0.34 1.35 Fail 3.66 ± 0.12 5.14 ± 0.37 1.41 Fail 2.92 ± 0.10 4.59 ± 0.34 1.57 Fail 3.39 ± 0.11 6.11 ± 0.44 1.80 Fail

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Table 7.08 (continued): Water Performance (External QA)

Analysis

QA Agent (pCi·L-1 ± 2 sigma)





Sr-90

0.451 ± 0.015 0.407 ± 0.065 0.90 0.596 ± 0.020 0.766 ± 0.093 1.29 0.440 ± 0.014 0.562 ± 0.077 1.28 0.459 ± 0.015 0.747 ± 0.098 1.63 Fail

Y-88 111000 ± 7000 144000 ± 6000 1.30 Fail 136000 ± 9000 151000 ± 9000 1.11 Fail

Zn-65

7.96 ± 0.26 9.44 ± 1.36 1.19 9.21 ± 0.30 10.2 ± 1.4 1.11 6.03 ± 0.20 5.96 ± 1.09 0.99 8.73 ± 0.29 9.29 ± 1.36 1.06

Table 7.09: Food/Vegetation Performance (External QA)

Analysis QA Agent (pCi·kg-1 ± 2

NB Power (pCi·kg-1 ± 2 sigma)


Ce-141 8.40 ± 0.27 9.40 ± 1.16 1.128.66 ± 0.28 10.8 ± 1.3 1.25

Co-58 8.58 ± 0.28 9.88 ± 1.23 1.158.92 ± 0.29 10.7 ± 1.4 1.20

Co-60 10.4 ± 0.3 11.2 ± 1.1 1.0710.8 ± 0.4 13.1 ± 1.2 1.2140.7 ± 9.6 37.7 ± 3.0 0.9357.7 ± 13.6 63.6 ± 4.0 1.10

Cr-51 8.66 ± 0.28 10.8 ± 1.3 1.25

Cs-134

10.5 ± 0.3 10.7 ± 1.3 1.0110.8 ± 0.4 14.5 ± 2.1 1.34 Fail 39.6 ± 8.7 35.3 ± 3.4 0.8962.5 ± 13.7 61.1 ± 4.8 0.98

Cs-137 7.29 ± 0.24 7.73 ± 1.02 1.067.66 ± 0.25 10.2 ± 1.3 1.33 Fail 31.0 ± 6.9 29.2 ± 3.0 0.9438.1 ± 8.4 40.0 ± 3.7 1.05

Fe-59 7.36 ± 0.24 7.29 ± 1.96 0.997.59 ± 0.25 10.4 ± 2.4 1.37

K-40 1150 ± 260 1080 ± 90 0.941140 ± 260 1100 ± 90 0.96

Mn-54 7.59 ± 0.13 8.40 ± 1.09 1.117.84 ± 0.25 9.99 ± 1.31 1.27

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Table 7.09 (continued): Food/Vegetation Performance (External QA)

Analysis QA Agent (pCi·kg-1 ± 2 sigma)

NB Power (pCi·kg-1 ± 2 sigma)


Zn-65

14.2 ± 0.5 16.7 ± 2.5 1.17 14.8 ± 0.5 19.8 ± 3.0 1.34 Fail 104 ± 24 104 ± 10 0.99

62.5 ± 14.2 79.2 ± 8.5 1.27

Table 7.10: Soil Performance (External QA) Analysis QA Agent

(pCi·kg-1 ± 2 sigma)NB Power

(pCi·kg-1 ± 2 sigma)NB Power/ QA Agent

(ratio)

Am-241 45.9 ± 12.0 40.3 ± 5.4 0.88 32.5 ± 7.7 19.9 ± 5.0 0.61

Ce-141 7.84 ± 0.26 6.22 ± 1.02 0.79 8.73 ± 0.29 7.47 ± 1.16 0.86

Co-58 8.03 ± 0.26 7.22 ± 1.09 0.90 8.99 ± 0.29 8.25 ± 1.16 0.92

Co-60

9.73 ± 0.32 9.36 ± 1.02 0.96 10.9 ± 0.4 10.5 ± 1.1 0.96 203 ± 47 179 ± 8 0.88 297 ± 69 286 ± 12 0.96

Cs-134

9.84 ± 0.32 10.6 ± 1.4 1.08 10.9 ± 0.4 10.1 ± 0.9 0.93 128 ± 23 100 ± 8 0.79 202 ± 37 160 ± 12 0.79

Cs-137

9.66 ± 0.32 8.70 ± 1.16 0.90 10.5 ± 0.3 9.92 ± 1.31 0.94 159 ± 28 132 ± 8 0.83 248 ± 43 224 ± 13 0.90

Fe-59 6.88 ± 0.22 7.51 ± 1.81 1.09 7.66 ± 0.25 8.44 ± 2.03 1.10

K-40 392 ± 80 344 ± 28 0.88 392 ± 80 362 ± 30 0.92

Mn-54 7.07 ± 0.23 7.59 ± 1.09 1.07 7.92 ± 0.26 7.96 ± 1.16 1.00

Zn-65

13.3 ± 0.4 13.9 ± 1.7 1.05 14.9 ± 0.5 17.1 ± 1.9 1.14 90.7 ± 16.2 88.4 ± 6.1 0.98 108 ± 19 110 ± 8 1.02

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Table 7.11: Environmental TLD Performance (External QA)

Analysis QA Agent (mR ± 2 sigma)

NB Power (mR ± 2 sigma)


Gamma 118 ± 6 108 ± 17 0.91 7.03 Internal QA There are three parts to Internal QA:

1) duplicate samples – two samples collected at the same time and analysed separately 2) replicate analyses – two analyses done on the same sample 3) blind analyses – one person irradiates the TLDs and a different person performs the analysis

Duplicate samples and replicate analyses are employed as part of the overall quality assurance program. For those media where two samples can be obtained from the same location at the same time, similar analytical results are expected. This approach demonstrates that the samples are representative of the medium in that area. Where duplicate samples are not possible, e.g., air filters, a sample is counted twice to demonstrate reproducibility in the counting system. Tracking of results is done in a spreadsheet and performance is charted. If the range of the ratio (of the two detected measurements) plus or minus the combined uncertainty (95% confidence interval) includes 1.00, then performance is acceptable. See Table 7.13 for the frequency. There were 179 radionuclide comparisons performed. Ten of these had results outside expectations. The results are presented graphically in Figures 7.01 to 7.12 (plotted against the analysis date).

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Table 7.13: Internal Quality Assurance Frequency

Medium Duplicate/Replicate Number of

Radionuclide Comparisons

Analyses

Airborne Carbon Dioxide

Replicate analysis (single location) 12 LSC C-14

Airborne Iodines Replicate count (1 composite set) 28 Gamma

Airborne Particulates Replicate analysis 11 Gamma

24 Alpha/Beta

Food Replicate analysis 3 Gamma

Milk Duplicate sample 4 Gamma

Parshall Flume Replicate analysis 14 LSC H-3

LEM Composite Replicate analysis

21 Gamma

28 Alpha/Beta

15 Sr-89,90

Sea Food Replicate analysis 5 Gamma

Sediment / Soil Duplicate sample 10 Gamma

Environmental Gamma Duplicate sample 4 TLD

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Figure 7.01: Alpha Performance (Internal QA – duplicate/replicate)

Figure 7.02: Beta Performance (Internal QA – duplicate/replicate)

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Figure 7.03: Beryllium-7 Performance (Internal QA – duplicate/replicate)

Figure 7.04: Carbon-14 Performance (Internal QA – duplicate/replicate)

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Figure 7.05: Cobalt-60 Performance (Internal QA – duplicate/replicate)

Figure 7.06: Niobium-95 Performance (Internal QA – duplicate/replicate)

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Figure 7.07: Tritium Performance (Internal QA – duplicate/replicate)

Figure 7.08: Potassium-40 Performance (Internal QA – duplicate/replicate)

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Figure 7.09: Gamma Performance (Internal QA – duplicate/replicate)

Figure 7.10: Sb-124 Performance (Internal QA – duplicate/replicate)

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Figure 7.11: Strontium-90 Performance (Internal QA – duplicate/replicate)

Figure 7.12: Actinium-228, Cs-137 and Zr-95 Performance (Internal QA – duplicate/replicate)

Samples that are spiked by laboratory personnel play a minor role in the QA program. It is more desirable to purchase QA samples from an accredited QA laboratory. The only exception is the irradiation of environmental TLDs. Similar to External QA, one member of the lab staff irradiates the TLDs and a different person analyses the sample. Results of performance with these

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samples give an indication of the quality of measurements. Acceptable performance is defined as results within ± 15% of the expected value. The four separate tests were successful (five TLDs for each test). The results are presented in Figure 7.13.

Figure 7.13: Gamma Performance (Internal QA - spikes) 7.04 Program Audit The REMP audit frequency was changed to once every five years to align with the Canadian Standards Association (CSA) standard. The Nuclear Oversight Group (NOS) at PLNGS is the principal auditor, although other groups from within NB Power, the CNSC, or other utilities may be used. As part of its overall Management System, Point Lepreau has an Environmental Management System (EMS) in place that is registered to ISO 14001. Radiological releases to water and air are part of this system. There were three audits relating to the EMS during 2016. 7.05 Annual Review A review of the Radiation Environmental Monitoring Program (REMP) takes place each year. The requirement for this review is stated in IR-03541-HF02, Radiation Environmental Monitoring Program (REMP) and described in HPF-03541-EN04, Quality Assurance of the Environmental Program. All members of the lab take part in this formal review. Generally, all aspects of the program are examined to make sure that the objectives, as stated in the program description document, are being met.

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8 Non-Radiological Monitoring and Reporting 8.01 Ozone Depleting Substance In Canada, the federal government has legislation in place for the protection of the ozone layer and management of ozone-depleting substances and their halocarbon alternatives. The use and handling of these substances are regulated through the Federal Halocarbon Regulation, 2003 for refrigeration, air-conditioning, fire extinguishing, and solvent systems under federal jurisdiction. Point Lepreau Nuclear Generating Station is governed by the federal regulations. In 2016, there were no releases that required reporting to Environment Canada. Letters submitted to Environment Canada are sent to the CNSC staff as per Guidance in REGDOC 3.1.1 Section 3.5. 8.02 Domestic Waste Water Treatment (Sewage) (Approval to Operate S-2696) The domestic waste water is regulated by the provinces and territories in their jurisdictions, and through the Federal Wastewater System Effluent Regulations. Point Lepreau Nuclear Generating Station is governed federally and administered provincially. At Point Lepreau Nuclear Generating Station, an electronic report via Effluent Regulation Reporting Information System (ERRIS) is completed. The electronic submission frequency is determined on daily discharge flow of the facility. PLNGS electronic report was completed January 23, 2017. Based on the 2016 daily discharge flow, it was required to be completed electronically once during the year at the end of the calendar year. Also, a letter is submitted to New Brunswick Department of Environment and Local Government describing any discharge to an Overflow Points and Environmental Emergency that occurred during the year. This was submitted on January 26, 2017. The letter is required to be submitted within 45 days of the end of each year. The approval required to sample (grab or composite) on a quarterly basis but at least 60 days after any other samples. PLNGS collects and analyzes the effluent on a weekly basis to verify the performance of the facility. The sample collection and analysis is performed by Saint John Laboratory Services Ltd. They are accredited to Canadian Association for Laboratory Accreditation Inc. (CALA).

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Table 8.01 Electronic Data Submission to ERRIS

Owner New Brunswick Power Corporation Wastewater System: Point Lepreau Generating Station

Approval State: Approved

Reporting Reporting Period: January to December year: 2016

System Average Daily Effluent Volume (m³): 110.9Type: Continuous

Reporting Averaging Period: AnnuallyFrequency: Annually

Effluent Monitoring Data

Month Effluent Deposited?

January YesFebruary YesMarch YesApril YesMay YesJune YesJuly Yes

August YesSeptember YesOctober YesNovember YesDecember Yes

Number of days

that effluent was deposited

Total volume of effluent deposited (m³)

Average CBOD (mg/L) Limit: 25 mg/L

Average concentration of suspended solids(mg/L) Limit: 25 mg/L

345 44495.0 2.1 1.2

Acute Lethality Test Results Does your waste water system have Acute Lethality test sample (s) to report in this reporting period?(Required) No

This test is required when daily flow is greater than 2,500 m³.

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8.03 Waste Water Compliance (Approval to Operate I-7479) The wastewater compliance reports for PLNGS are submitted to New Brunswick Department of Environment and Local Government, based on the reporting Conditions of the Approval to Operate, as follows: The operation of the Industrial Wastewater Treatment System at PLNGS has an Approval to Operate (#I-7479) issued under the Water Quality Regulation – Clean Environment Act. It is valid from May 25, 2016 until April 30, 2021. Condition 44 states that “Within 60 days of the end of each year, The Approval Holder shall submit an Annual Environmental Report to the Department.” Samples are collected and analyzed daily for pH, suspended solids and hydrazine. From the daily samples, a monthly composite is prepared and analyzed for heavy metals (arsenic, barium, cadmium, chromium, copper, iron, lead, mercury, nickel, vanadium and zinc) and Total Petroleum Hydrocarbons (TPH). The daily sample analysis is performed by the Chemistry Department using procedures:

• CAP-78200-PH1; pH Measurement by Glass Combination Electrode • CLIP-78200-74; Accumet Excel Model 25 pH/Millivolt Meter • CAP-78200-SU2; Suspended Solid • CAP-78200-HY1; Hydrazine by P-Dimethylaminobenzaldehyde • CLIP-78200-22; Varian Cary 50 UV/VIS Spectrometer • CMP-78200-03; Varian UV/VIS Spectrometer Model Cary

The heavy metals and the TPH are analysis is performed by Saint John Laboratory Services Ltd. They are accredited to Canadian Association for Laboratory Accreditation Inc. (CALA). The annual report is sent to the CNSC staff as per Guidance in REGDOC 3.1.1 Section 3.5. 8.04 Air Emission (NPRI) Site conventional air emissions are controlled to meet regulatory requirements, prevent pollution, reduce emissions, and to minimize environmental impacts. Point Lepreau Nuclear Generating Station no longer requires an air quality approval to operate the Auxiliary Volcano Boiler and Diesel Generators. The fuel consumption and emissions for 2016 were tracked and calculated for possible reporting purposes to the National Pollutant Release Inventory (NPRI) should emissions meet reporting thresholds. We do not need to report the emissions to the Department of Environment and Local Government. During the year 1,915 barrels (304,485 liters) of Type 2 Light Oil and 3,398 barrels (540,282 liters) of Type B Diesel Fuel were consumed at the station. The preliminary analysis indicate the light fuel oil had an average energy content of 5.74 million BTUs per barrel, an average ash content of 0.0003 percent, and an average sulphur content of 0.0079 percent. The preliminary

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analysis indicate the diesel fuel oil had an average energy content of 5.58 million BTUs per barrel, an average ash content of 0.0005 percent, and an average sulphur content of 0.0009 percent. Fuel analysis results are obtained from the AmSpec Services analysis results sent to the Chemistry Department at PLNGS while fuel consumption figures are provided by the NB Power Fuels Group. During the year the annual emissions were calculated and are shown in Table 8.02

Table 8.02 Annual Emissions (2016)

8.05 Chlorine There is currently no chlorine disinfection on site at the Point Lepreau Nuclear Generating Station. There is a sodium hypochlorite system utilized during maintenance of specific sections of the domestic waste water works. 8.06 Ammonia There is currently no requirement to measure ammonia in the effluent at Point Lepreau Nuclear Generating Station. 8.07 Hydrazine Hydrazine is reported with the Inactive Waste Water approval to Operate I-7475. Samples are collected and analyzed daily at the lagoon discharge, and the Ditch. 8.08 EMS Program Audit The Point Lepreau Nuclear Generating Station is certified to ISO 14001:2004 standard. The certification cycle is a period of three years. The 2016 was a registration audit year. During the audit, the auditor identified one (1) minor nonconformity with eight (8) opportunities for improvement and one (1) observation. All findings were minor in nature and are being tracked through PLNGS’s internal Corrective Action Program.

Parameter TonnesCarbon Dioxide 2,515 Sulphur Dioxide 0.07 Nitrogen Dioxide 6.80 Particulate Matter 0.35

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8.09 Self-Assessments

In 2016, the environmental group performed one self-assessment:

ISO 14001:2015 Gap Analysis A clause by clause gap analysis was performed and identified gaps between the ISO14001:2004 standard and the new ISO14001:2015 standard. The proposed actions were documented as part of continuous improvement.

9 Reports and Studies A gap analysis for alignment to the CSA Standard N288.4-10, Environmental monitoring programs at Class I nuclear facilities and uranium mines and mills was conducted in 2012. Implementation plans were made in 2013. Alignment to the Canadian Standards Association (CSA) standards N288.4-10, Environmental monitoring programs at Class I nuclear facilities and uranium mines and mills and N288.5-11, Effluent monitoring programs at Class I nuclear facilities and uranium mines and mills was progressed in 2016. The following were issued in 2016:

• Ecological risk assessment report (Point Lepreau Generating Station- Site Wide Risk Assessment: Human Health and Ecological Risk Assessment, February 2016, Arcadis Canada Inc) as per N288.6-12, Environmental risk assessments at class I nuclear facilities and uranium mines and mills).

• Fish entrainment report (Point Lepreau Generating Station- Final: Entrainment Monitoring Plan and Implementation for Point Lepreau Generating Station, March 2016, Arcadis Canada Inc.).

• Fish impingement report ( NB Power- Progress Report Impingement Monitoring at Point Lepreau Generating Station 2013-2014, March 2016, Arcadis Canada Inc.).

Canadian Nuclear Laboratories (CNL) continued their work to help the station close the gaps and implement the standards for PLNGS.

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Appendix A: Statistics, Detection Limits, and Dose at Detection Limits A1 Statistics The following statistical conventions are applied in the analysis of each sample:

• Detection limits are defined following the method described by Lochamy in NBS Special Publication 456, Measurements for the Safe Use of Radiation (US Department of Commerce, 1976). The lower limit of detection (LLD) at the 99% confidence level is defined as 6.58 Sb, where Sb is the standard deviation of the appropriate radiation background measurement. This LLD corresponds to that amount of activity in a sample that will yield a net count greater than 3.29 Sb, or the so-called critical level (CL), with 99% probability. Thus, the LLD specifies the theoretical capability of the system to detect a given amount of radioactivity, whereas the CL is used to determine whether an actual activity measurement should be considered detected. Any net measurement greater than 3.29 Sb is considered detected at the 99% confidence level. This also implies a one percent probability of stating that activity is present when it is not (false positive). If activity is present at the LLD level (6.58 Sb), there is a one percent probability of stating that activity is not present when it is (false negative).

• The CL of 3.29 Sb and LLD of 6.58 Sb apply in those analytical systems where the

background levels are either not well defined, or where there is a relationship between the background levels and the detected signal above background, as in Ge gamma spectroscopy. Where the background readings are well defined and are independent of sample readings, as in the TLD data, the CL is 2.33 Sb and the LLD is 4.66 Sb.

• In most of the tables of data (Section 4.0), it is this Critical Level that appears in

column 2. • Unless otherwise indicated, the precision of the measurements reported here is given as

± 1.96 Sa (95% confidence level), where Sa is the standard deviation of the activity measurement.

• The value and standard deviation are reported with two significant figures using modified

scientific notation, for example 0.032 is expressed as 3.2E-02. The lower limits of detection (LLD) of all radionuclides in the various sample media are shown in Tables A.01 to A.11. The Annual Dose is to the Representative Person. The LLDs are based on typical data. Decay of radionuclides is accounted for in the LLD calculations except for H-3 and C-14 (long half-lives). The major assumptions are that the sample is taken at one kilometre from the point of emissions and that the level is maintained for the year. Milk is assumed to be from a cow pastured at 1.5 km, fish and lobster are caught at the Condenser Cooling Water (CCW) outlet and sediment, dulse, seawater and clams are collected at Dipper Harbour. The CSA recommends, where technically feasible, that all measurements achieve LLDs less than that which would result in a dose of 5 μSv to the Representative Person. Most radionuclides pass

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this criterion. The major exceptions are noble gases. Detection of this group is through TLD measurements (20 μSv dose to the Representative Person at the LLD). However, the noble gas spectrometer on the GEM allows for a much smaller LLD calculation. Other exceptions are Ba-140 in soil and sediment (10 to 12 μSv); Ru-106 in water and clams (7 to 17 μSv); Ce-144 in water (11 μSv); and I-131 in food (8 μSv). Effluent analyses show these radionuclides are not major components of emissions. Part of the QA process identifies those LLDs or activities that do not meet this target. A1.01 Air A1.01.01 Airborne Particulates Typical LLDs are given for a 2400 m3 sample that is counted for 5000 s. The LLDs are decay corrected to the midpoint between the start and end of sampling, except for the gross alpha/beta results which represent the long-lived activity present a few days after sample collection. Gross alpha/beta is for trending only. A1.01.02 Airborne Radioiodines A typical LLD for I-131 is approximately 9E-05 Bq·m-3 (for a 2400 m3 sample, counted for 50 000 s), which is decay corrected to the midpoint between the start and end of sampling. A1.01.03 Airborne Tritium The LLD is approximately 1E-01 Bq·m-3 of air for a typical sample of 10 to 70 m3 (counted for 100 min). Due to the long half-life and relatively short period of time between sampling and analysis, decay correction is not applied. A1.01.04 Airborne Carbon-14 A typical LLD is approximately 4E-02 Bq·m-3 of air for a 30 m3 sample (counted for 100 min). Due to the long half-life and relatively short period of time between sampling and analysis, decay correction is not applied. A1.01.05 TLD The LLD is about 20 μSv. For typical quarterly measurements in the region of 150-200 μSv, measurements can be made to ± 10% at the 95% confidence level.

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Table A.01 Annual Dose at the LLD for Air

Nuclide LLD (Bq·m-3)

Dose at LLD (μSv)

Concentration That Gives 5 μSv (Bq·m-3)

H-3 9.6E-02 4.8E-02 9.9E+00 C-14 4.0E-02 1.9E+00 1.0E-01 Cr-51 5.8E-04 3.2E-03 9.2E-01 Mn-54 7.8E-05 9.2E-02 4.3E-03 Fe-59 1.7E-04 6.1E-02 1.4E-02 Co-58 8.0E-05 3.5E-02 1.2E-02 Co-60 8.2E-05 1.7E+00 2.4E-04 Zn-65 1.9E-04 3.3E-01 2.9E-03 Kr-85 2.0E+01 μSv 2.0E+01 5.0E+00 μSv

Kr-85m 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Kr-87 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Kr-88 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Zr-95 1.3E-04 1.1E-01 6.2E-03 Nb-95 9.4E-05 9.9E-02 4.7E-03 Ru-103 7.4E-05 8.1E-03 4.5E-02 Ru-106 6.0E-04 1.0E+00 2.9E-03

Ag-110m 6.2E-05 2.2E-01 1.4E-03 I-131 8.4E-05 1.6E-01 2.5E-03

Xe-131m 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Xe-133 2.0E+01 μSv 2.0E+01 5.0E+00 μSv

Xe-133m 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Xe-135 2.0E+01 μSv 2.0E+01 5.0E+00 μSv

Xe-135m 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Xe-138 2.0E+01 μSv 2.0E+01 5.0E+00 μSv Cs-134 6.4E-05 4.3E-01 7.4E-04 Cs-137 6.6E-05 1.6E+00 2.0E-04 Ba-140 4.8E-04 8.9E-02 2.7E-02 La-140 2.0E-04 2.5E-03 4.1E-01 Ce-141 7.6E-05 4.8E-03 7.9E-02 Ce-144 2.2E-04 2.7E-01 4.0E-03

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A1.02 Milk The LLDs in Table A.02 apply to the midpoint between the start and end of sampling for a 3.6 L sample counted for 50 000 s for gamma and a 6 mL sampled counted for 100 min for tritium.

Table A.02 Annual Dose at the LLD for Milk

Nuclide LLD (Bq·L-1)

Dose at LLD (μSv)

Concentration That Gives 5 μSv (Bq·L-1)

H-3 2.4E+01 3.1E-01 3.9E+02 Cr-51 6.4E-01 1.0E-02 3.1E+02 Mn-54 9.2E-02 1.9E-02 2.5E+01 Fe-59 2.2E-01 2.2E-01 5.1E+00 Co-58 9.0E-02 7.5E-02 6.0E+00 Co-60 1.1E-01 9.0E-01 6.1E-01 Zn-65 2.4E-01 5.3E-01 2.3E+00 Zr-95 1.6E-01 4.3E-02 1.8E+01 Nb-95 9.2E-02 1.2E-01 3.8E+00 Ru-103 8.4E-02 1.9E-02 2.2E+01 Ru-106 7.8E-01 2.7E+00 1.4E+00

Ag-110m 8.2E-02 5.5E-02 7.4E+00 I-131 9.4E-02 1.8E+00 2.6E-01

Cs-134 7.8E-02 3.1E-01 1.3E+00 Cs-137 9.8E-02 3.1E-01 1.6E+00 Ba-140 3.4E-01 2.1E-01 8.1E+00 La-140 1.1E-01 8.9E-02 6.1E+00 Ce-141 1.2E-01 3.0E-02 2.1E+01 Ce-144 5.0E-01 9.5E-01 2.6E+00

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A1.03 Water The LLDs in Table A.03 apply to the midpoint between the start and end of sampling for a 3.6 L sample counted for 5000 s for gamma and a 6 mL sampled counted for 100 min for tritium. Alpha/beta results (a 100-500 mL sample counted for 100 min) represent the long-lived activity present several days after sample collection. The LLDs are based on typical data for precipitation water. Since decay of radionuclides is accounted for in the LLD calculations, well water and other water sample types will have lower LLDs. The major assumptions are that the sample is taken at one kilometre from the point of emissions, that the level is maintained for the year and the sample type is the major source of drinking water. Obviously, this is not the case but it gives a simple “worst case” that is easy to monitor and calculate.

Table A.03 Annual Dose at the LLD for Water


Dose at LLD (μSv)


H-3 2.4E+01 3.4E-01 3.6E+02 Cr-51 5.4E+01 7.4E-02 3.7E+03 Mn-54 5.0E-01 1.7E-01 1.4E+01 Fe-59 1.3E+00 9.1E-01 7.1E+00 Co-58 5.6E-01 3.7E-01 7.5E+00 Co-60 4.6E-01 4.5E+00 5.1E-01 Zn-65 1.1E+00 2.3E+00 2.4E+00 Zr-95 9.8E-01 4.0E-01 1.2E+01 Nb-95 6.8E-01 4.0E-01 8.5E+00 Ru-103 6.4E-01 1.8E-01 1.8E+01 Ru-106 4.6E+00 1.7E+01 1.4E+00

Ag-110m 4.6E-01 6.2E-01 3.7E+00 I-131 2.4E+00 3.9E+00 3.1E+00

Cs-134 4.4E-01 4.8E+00 4.6E-01 Cs-137 5.2E-01 3.9E+00 6.6E-01 Ba-140 5.4E+00 2.7E+00 1.0E+01 La-140 2.2E+00 9.1E-01 1.2E+01 Ce-141 8.4E-01 3.4E-01 1.2E+01 Ce-144 2.4E+00 1.1E+01 1.1E+00

A1.04 Food

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The LLDs in Table A.04 apply to the time of sample collection. Samples vary in size and are counted for 5000 s. The LLDs are based on typical data for garden vegetables.

Table A.04 Annual Dose at the LLD for Food

Nuclide LLD (Bq·kg-1)

Dose at LLD (μSv)

Concentration That Gives 5 μSv (Bq·kg-1)

Cr-51 3.0E+01 5.9E-02 2.5E+03 Mn-54 3.4E+00 1.3E-01 1.3E+02 Fe-59 7.8E+00 8.4E-01 4.6E+01 Co-58 3.6E+00 3.0E-01 6.0E+01 Co-60 3.8E+00 3.9E+00 4.9E+00 Zn-65 9.0E+00 2.2E+00 2.1E+01 Zr-95 6.2E+00 3.3E-01 9.4E+01 Nb-95 4.0E+00 3.6E-01 5.6E+01 Ru-103 3.8E+00 1.7E-01 1.1E+02 Ru-106 3.0E+01 1.3E+01 1.1E+01

Ag-110m 3.0E+00 4.7E-01 3.2E+01 I-131 1.0E+01 6.9E+00 7.6E+00

Cs-134 3.0E+00 3.6E+00 4.2E+00 Cs-137 3.4E+00 2.9E+00 6.0E+00 Ba-140 2.4E+01 3.5E+00 3.5E+01 La-140 9.4E+00 1.2E+00 4.0E+01 Ce-141 4.2E+00 1.9E-01 1.1E+02 Ce-144 1.4E+01 4.9E+00 1.4E+01

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A1.05 Soil The LLDs in Table A.05 apply to the time of sample collection. Samples of approximately 200 g are counted for 5000 s.

Table A.05 Annual Dose at the LLD for Soil


Dose at LLD (μSv)


Cr-51 4.0E+01 2.5E-01 7.9E+02 Mn-54 5.8E+00 1.2E+00 2.5E+01 Fe-59 1.2E+01 3.1E+00 1.9E+01 Co-58 5.0E+00 1.1E+00 2.2E+01 Co-60 5.8E+00 3.2E+00 9.1E+00 Zn-65 1.3E+01 1.7E+00 3.9E+01 Zr-95 1.0E+01 5.1E+00 9.9E+00 Nb-95 6.0E+00 9.9E-01 3.0E+01 Ru-103 4.8E+00 5.1E-01 4.7E+01 Ru-106 4.6E+01 1.9E+00 1.2E+02

Ag-110m 5.2E+00 2.7E+00 9.7E+00 I-131 6.8E+00 5.2E-01 6.6E+01

Cs-134 5.2E+00 1.5E+00 1.7E+01 Cs-137 5.6E+00 7.1E-01 3.9E+01 Ba-140 2.2E+01 1.1E+01 9.6E+00 La-140 7.2E+00 * * Ce-141 6.8E+00 1.2E-01 2.8E+02 Ce-144 2.4E+01 2.9E-01 4.2E+02 TLD 2.0E+01 μSv 2.0E+01 5.0E+00 μSv

*Dose for Ba-140 assumes equilibrium with La-140 (contribution from both)

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A1.06 Seawater The LLDs in Table A.06 apply to the time of sample collection for a 3.6 L sample counted for 5000 s for gamma; and a 6 mL sampled counted for 100 min for tritium. The dose is small due to the simple facts that the frigid waters of the Bay of Fundy discourage immersion and salt water is not consumable.

Table A.06 Annual Dose at the LLD for Seawater


Dose at LLD (μSv)


H-3 2.4E+01 9.2E-11 1.3E+12 Cr-51 2.2E+00 2.6E-10 4.3E+10 Mn-54 2.8E-01 7.9E-10 1.8E+09 Fe-59 6.2E-01 2.6E-09 1.2E+09 Co-58 2.8E-01 9.1E-10 1.5E+09 Co-60 3.2E-01 2.4E-09 6.8E+08 Zn-65 6.8E-01 1.3E-09 2.6E+09 Zr-95 5.2E-01 1.2E-09 2.2E+09 Nb-95 3.0E-01 9.3E-10 1.6E+09 Ru-103 2.8E-01 4.4E-10 3.2E+09 Ru-106 2.6E+00 1.6E-09 8.3E+09

Ag-110m 2.6E-01 2.3E-09 5.7E+08 I-131 3.6E-01 2.3E-09 8.0E+08

Cs-134 2.6E-01 1.3E-09 1.0E+09 Cs-137 3.0E-01 5.2E-10 2.9E+09 Ba-140 1.2E+00 2.6E-08 2.4E+08 La-140 4.6E-01 * * Ce-141 4.0E-01 1.1E-10 1.8E+10 Ce-144 1.6E+00 2.7E-10 3.0E+10

* Dose for Ba-140 assumes equilibrium with La-140 (contribution from both)

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A1.07 Clams Typical LLDs are given in Table A.07 for the edible portions of clams, decay corrected to the time of sample collection. Samples of varying size are counted for 5000 s. The major assumptions are that the sample is taken at Dipper Harbour and that the level is maintained for the year.

Table A.07 Annual Dose at the LLD for Clams


Dose at LLD (μSv)


Cr-51 5.0E+01 2.0E-02 1.3E+04 Mn-54 7.0E+00 6.5E-02 5.4E+02 Fe-59 1.4E+01 3.1E-01 2.3E+02 Co-58 7.2E+00 1.3E-01 2.7E+02 Co-60 6.4E+00 1.8E+00 1.8E+01 Zn-65 1.4E+01 8.8E-01 7.8E+01 Zr-95 1.2E+01 1.5E-01 3.7E+02 Nb-95 6.6E+00 1.4E-01 2.3E+02 Ru-103 6.0E+00 5.5E-02 5.5E+02 Ru-106 5.8E+01 6.5E+00 4.5E+01

Ag-110m 5.8E+00 2.2E-01 1.3E+02 I-131 7.2E+00 9.5E-01 3.8E+01

Cs-134 6.6E+00 1.6E+00 2.1E+01 Cs-137 6.8E+00 1.5E+00 2.2E+01 Ba-140 2.4E+01 7.7E-01 1.6E+02 La-140 9.4E+00 2.2E-01 2.1E+02 Ce-141 7.4E+00 8.0E-02 4.6E+02 Ce-144 3.2E+01 2.6E+00 6.3E+01

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A1.08 Fish Typical LLDs are given in Table A.08 for the edible portions of fish, decay corrected to the time of sample collection. Samples of varying size are counted for 5000 s.

Table A.08 Annual Dose at the LLD for Fish


Dose at LLD (μSv)


Cr-51 1.3E+01 1.6E-02 4.0E+03 Mn-54 1.5E+00 5.1E-02 1.5E+02 Fe-59 3.8E+00 2.8E-01 6.8E+01 Co-58 1.5E+00 9.2E-02 8.0E+01 Co-60 1.4E+00 1.3E+00 5.4E+00 Zn-65 3.0E+00 7.0E-01 2.2E+01 Zr-95 2.2E+00 1.1E-01 1.0E+02 Nb-95 1.4E+00 1.1E-01 6.6E+01 Ru-103 1.5E+00 4.9E-02 1.5E+02 Ru-106 1.1E+01 4.4E+00 1.2E+01

Ag-110m 1.2E+00 1.7E-01 3.5E+01 I-131 7.8E+00 1.3E+00 3.1E+01

Cs-134 1.0E+00 1.2E+00 4.5E+00 Cs-137 1.4E+00 1.0E+00 7.1E+00 Ba-140 1.0E+01 7.8E-01 6.4E+01 La-140 4.6E+00 2.4E-01 9.6E+01 Ce-141 1.8E+00 6.0E-02 1.5E+02 Ce-144 5.8E+00 1.6E+00 1.8E+01

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A1.09 Lobster Typical LLDs are given in Table A.09 for the edible portions of lobster, decay corrected to the time of sample collection. Samples of varying size are counted for 5000 s.

Table A.09 Annual Dose at the LLD for Lobster


Dose at LLD (μSv)


Cr-51 3.0E+01 1.3E-02 1.2E+04 Mn-54 2.8E+00 2.1E-02 6.7E+02 Fe-59 9.0E+00 1.5E-01 2.9E+02 Co-58 3.2E+00 6.7E-02 2.4E+02 Co-60 3.8E+00 5.4E-01 3.5E+01 Zn-65 7.8E+00 3.4E-01 1.2E+02 Zr-95 5.4E+00 6.8E-02 4.0E+02 Nb-95 4.4E+00 9.0E-02 2.4E+02 Ru-103 4.0E+00 3.1E-02 6.4E+02 Ru-106 3.0E+01 2.4E+00 6.3E+01

Ag-110m 3.4E+00 8.8E-02 1.9E+02 I-131 1.7E+01 3.3E+00 2.6E+01

Cs-134 2.8E+00 6.4E-01 2.2E+01 Cs-137 3.4E+00 4.5E-01 3.8E+01 Ba-140 3.4E+01 1.2E+00 1.4E+02 La-140 1.2E+01 4.2E-01 1.4E+02 Ce-141 4.4E+00 4.3E-02 5.1E+02 Ce-144 1.3E+01 8.7E-01 7.4E+01

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A1.10 Dulse Typical LLDs are given in Table A.10 for dulse, decay corrected to the time of sample collection. Samples of varying size are counted for 5000 s. The major assumptions are that the sample is taken at Dipper Harbour and that the level is maintained for the year.

Table A.10 Annual Dose at the LLD for Dulse

Nuclide

LLD (Bq·kg-1)

Dose at LLD (μSv)


Cr-51 2.0E+01 2.4E-03 4.2E+04 Mn-54 3.4E+00 7.4E-03 2.3E+03 Fe-59 8.0E+00 4.4E-02 9.0E+02 Co-58 3.4E+00 1.5E-02 1.1E+03 Co-60 3.4E+00 2.1E-01 7.9E+01 Zn-65 8.2E+00 1.1E-01 3.9E+02 Zr-95 6.6E+00 1.6E-02 2.1E+03 Nb-95 3.6E+00 1.9E-02 9.5E+02 Ru-103 2.8E+00 7.1E-03 2.0E+03 Ru-106 2.6E+01 6.7E-01 2.0E+02

Ag-110m 3.0E+00 2.3E-02 6.4E+02 I-131 5.4E+00 3.0E-01 9.1E+01

Cs-134 2.8E+00 1.9E-01 7.3E+01 Cs-137 3.2E+00 1.3E-01 1.2E+02 Ba-140 1.6E+01 1.6E-01 4.9E+02 La-140 5.4E+00 2.8E-02 9.7E+02 Ce-141 3.4E+00 8.8E-03 1.9E+03 Ce-144 1.4E+01 2.4E-01 2.9E+02

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A1.11 Sediment The LLDs in Table A.11 apply to the time of sample collection. Samples weighing approximately 200 g are counted for 5000 s. The major assumptions are that the sample is taken at Dipper Harbour and that the level is maintained for the year.

Table A.11 Annual Dose at the LLD for Sediment


Dose at LLD (μSv)


Cr-51 1.7E+01 2.1E-01 4.2E+02 Mn-54 2.8E+00 7.9E-01 1.8E+01 Fe-59 6.2E+00 2.3E+00 1.3E+01 Co-58 2.6E+00 8.4E-01 1.5E+01 Co-60 2.8E+00 2.3E+00 6.1E+00 Zn-65 6.8E+00 1.3E+00 2.7E+01 Zr-95 4.8E+00 3.9E+00 6.1E+00 Nb-95 3.0E+00 7.2E-01 2.1E+01 Ru-103 2.4E+00 3.9E-01 3.1E+01 Ru-106 2.0E+01 1.5E+00 6.6E+01

Ag-110m 2.2E+00 2.1E+00 5.3E+00 I-131 3.4E+00 4.7E-01 3.6E+01

Cs-134 2.0E+00 1.2E+00 8.7E+00 Cs-137 2.8E+00 6.2E-01 2.3E+01 Ba-140 1.2E+01 1.0E+01 5.8E+00 La-140 3.8E+00 * * Ce-141 3.0E+00 8.9E-02 1.7E+02 Ce-144 1.1E+01 2.1E-01 2.7E+02

gamma meter 0.01 μSv·h-1 3.0E+00 1.7E-02 * Dose for Ba-140 assumes equilibrium with La-140 (contribution from both)

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Appendix B: Sample Collection and Analytical Techniques B1 Analytical Techniques All environmental samples are analysed at the Health Physics Fredericton Laboratory. The following pages provide a general summary of the analytical techniques used in the laboratory. Sample collection, preparation and analysis are briefly described, but can be found in detail in the laboratory procedures. The major analytical techniques and the instruments used in routine environmental analyses are summarised in the Table B.01.

Table B.01 Summary of Analytical Techniques

Analytical Technique Instrumentation

Gamma Spectroscopy

Canberra 24% efficient* intrinsic, Ge detector in an Applied Physical Technology 10 cm graded lead cave; Canberra S-100 MCA

Liquid Scintillation (tritium and C-14)

Beckman LS 6000TA Liquid Scintillation Counter

Gross Alpha/Beta (Wet Chemical Analysis for Sr-89 and Sr-90)

Tennelec LB-5100 Alpha/Beta Counting System and Protean WPC 9550 Counting System

Gamma Surveys

Eberline Model FH 40G-10 low range gamma survey meter (range 10 nSv·h-1 to 1 Sv·h-1 for 30 keV to 3 MeV photons).

Thermoluminescent Dosimetry Panasonic UD-7900U Automatic and UD-716AGL TLD Readers and UD-804A1 (CaSO4) dosimeters

*relative to a 3x3 inch sodium iodide detector

In gamma spectroscopy analysis, all significant peaks in the spectrum are identified either by reference to a database library of about 150 radionuclides, or by manual reference to compilations of all known radionuclides. In addition, approximately 20 selected radionuclides are specifically searched for in every sample with the exception of Air Iodine samples in which only I-131 is selected. The selected radionuclides include those that are produced in PLNGS, and which would be readily detectable because of their abundance (high fission yield) and high branching ratios for gamma emissions. Naturally occurring gamma emitters, with the exception of Be-7, K-40 and Ac-228, are not included in this report. These excepted radionuclides are sometimes useful as general indicators of the consistency of the analytical techniques.

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The peak search and analysis program SAMPO is used to process spectra. The library of radionuclides uses data of the Oak Ridge Laboratory. There are three categories of radionuclides evaluated:

1) selected nuclides of key fission and activation products 2) all other identified radionuclides, including natural radionuclides 3) detected energy peaks for which no identification can be readily made.

The three categories cover all possible eventualities in a spectral analysis and ensure that no significant radionuclides or photon energies will be overlooked. The usefulness of gross alpha/beta analysis lies primarily in showing trends and determining whether more detailed analyses should be done. The reported alpha and beta values are assessed with respect to Am-241 and Sr-Y-90 calibration sources, respectively. Wet chemical analysis for Sr-89,90 on GEM and LEM samples follows a method developed by Eichrom Industries Inc.(20) using a strontium specific chromatography resin. This method is similar to test method 05811-95 issued by the American Society of Tests and Materials (ASTM). Liquid samples, other than milk, are acidified upon receipt to keep radionuclides from plating out on the container walls. Perishable samples are refrigerated or frozen. B2 Sample Collection and Analysis B2.01 Airborne Particulates Airborne particulates are collected on a 47 mm diameter Gelman Type A glass fibre filter, through which air is drawn at about 60 L·min-1 for a 28 day continuous sample. The volume of air sampled (approximately 2400 m3) is measured with an in-line integrating dry gas meter. Every month the filters are replaced and the used ones are returned to the laboratory for analysis. Sampling is, therefore, continuous throughout the year. Air particulate filters are analysed by gamma spectroscopy as soon as possible after collection to ensure the detection of any short lived gamma emitters that may be present, and to minimise any decay corrections. Samples are counted for 5000 s on the Ge detector. Approximately three days after the end of the sample collection interval, each filter is counted on one of the alpha beta counters for 100 minutes for the simultaneous determination of gross alpha and gross beta activities. Counting is delayed to allow for the decay of the short-lived radon progeny that would otherwise complicate the analysis. If alpha/beta levels are detected at twice the normal level, further investigation is initiated by longer gamma counts or radiostrontium determinations.

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If levels of Sr-89,90, indicating one percent of the weekly DRL, are detected in the chemical analysis of GEM filters, then the air monitoring station particulate filters are also to be analysed for these radionuclides. B2.02 Airborne Radioiodines Airborne radioiodines are collected in an activated charcoal cartridge placed downstream of the particulate filter. The cartridges are from F&J Specialty Products (TE3C 20x40 mesh TEDA). Approximately 2400 m3 of air is sampled continuously over 28 days at a flow rate of about 60 L·min-1. The volume of air sampled is measured with an in-line integrating dry gas meter. Iodine-131 is the major nuclide of interest on the charcoal cartridges. The cartridges are counted in groups of four for 50 000 s on the gamma spectrometer. Counts are performed as soon as possible after collection because of the relatively short-half life of I-131 (8 days). If radioiodines, believed to have originated from PLNGS, are detected, then the cartridges are re-analysed individually. Fission product radioiodines other than I-131, with much shorter half-lives (minutes to hours), decay before they reach the sample location or during the time the sample is being collected. If a significant release of radioiodines were noted from the station in this interval, the samples would be changed and analysed earlier to minimise errors from decay corrections. B2.03 Airborne Tritium Air is passed through a molecular sieve container (Advanced Specialty Gas Equipment type 13X sieve material) to extract water vapour from the sampled air. Sample volume is measured with a mass flow controller (MFC) (Alicat Scientific Inc. MC-1SLPM-0). Sampling is continuous at each location throughout the year. Since the amount of water absorbed by the molecular sieve from a given volume of air depends upon absolute humidity, flow rates are adjusted with a MFC to avoid saturation of the sieve material and to ensure adequate sample collection. For tritium analysis by liquid scintillation counting, 6 mL of water taken from the molecular sieve condensate is counted for 100 minutes. B2.04 Airborne Carbon-14 An aquarium pump bubbles air through 2N NaOH (1 L), into which carbon dioxide and its C-14 component is absorbed. Carbon dioxide is regenerated from the resulting sodium carbonate by acidification of the 2N NaOH solution and then analysed for the determination of C-14 activity. The carbon dioxide is passed through a silica gel trap to remove moisture and tritium and then absorbed into the chemical Carbo-sorb® E until saturation is reached. After the addition of the scintillation cocktail Permafluor® E+, the sample is analysed for 100 minutes by liquid scintillation counting.

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B2.05 Environmental Gamma Radiation (TLD) The environmental TLD is composed of three elements of calcium sulphate with lead filtration of 700 mg·cm-2. The badge is sealed in plastic, placed in a screw cap plastic container and suspended approximately 1 m above the ground for a period of three months. This arrangement measures the ambient gamma dose, whether it is from activity in the air, from the ground or cosmic in origin. Readout is by a Panasonic Automatic Reader. For typical quarterly measurements in the region of 150-200 μSv, measurements can be made to ±10% at the 95% confidence level. B2.06 Soil Soil samples are collected in undisturbed locations away from nearby buildings or trees. Level areas with some vegetation are preferred. A representative sample (approximately 1.6 kg) of the top 25 mm of a 20 cm by 20 cm area of soil is placed in a disposable polyethylene container. The soil is air dried overnight. If excessive moisture is present, the sample is dried on a disposable aluminum tray (at 100 °C). Composed organic matter and stones are removed. Approximately 0.25 kg of dry soil is counted by gamma spectroscopy for 5000 s. B2.07 Food Garden produce and berries, which are either collected or purchased, require no special preparation. The edible portion is put in a calibrated container and weighed. The sample is counted by gamma spectroscopy for 5000 s. B2.08 Milk A 4L sample is purchased and placed in a clean polyethylene container. For gamma spectroscopy, a 3.6 L portion is measured into a marinelli beaker. Approximately 100 mL is distilled, and a 6 mL aliquot of the distillate is analysed for H-3 by liquid scintillation counting. Count times are 50 000 s for gamma spectroscopy and 100 min for tritium analysis. B2.09 Water A 4L sample of well water, pond water, lake water or surface runoff is collected in a clean polyethylene container. A portion is removed for tritium analysis, and the remainder is acidified (15 mL of 70% nitric acid per 4 L sample). Of this, 3.6 L is measured into a marinelli beaker for gamma spectroscopy. After gamma analysis, well water samples (125-500 mL, depending upon the historical content

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of dissolved solids) are evaporated until dry on stainless steel planchets for gross alpha/beta analysis. For tritium analysis, a 6 mL aliquot is analysed by liquid scintillation counting. For gamma spectroscopy, the sample is counted for 5000 s. For tritium and gross alpha/beta analyses, samples are counted for 100 min. A level twice the normal level for alpha/beta will initiate further investigation by longer gamma counts and/or Sr-89,90 analyses. Measurements of gross alpha and beta are made approximately two weeks after sample collection. This delay avoids analytical interference from radon progeny, which decay with a half-life of about 3.8 days. Naturally occurring radon and radon progeny are present in well waters everywhere and are known to reach elevated concentrations in many New Brunswick locations. B2.10 Vegetation The only vegetation types routinely collected and analysed are tree lichen (Spanish moss) and various ground mosses such as Cladonia and Lycopodium. They concentrate a wide range of radionuclides, both natural and man-made. This makes vegetation a sensitive indicator of radionuclides in the environment even though they are not identified in the pathway to humans. About 25 g or more of each of the samples is collected and air-dried before analysis. No special preparation is required. The sample is placed in a calibrated container, weighed and counted by gamma spectroscopy for 5000 s. B2.11 Precipitation Various forms of precipitation are collected continuously throughout the year. A portion is removed for tritium analysis and the remainder is acidified (15 mL of 70% nitric acid per 4 L sample). For gamma spectroscopy, 3.6 L is measured into a marinelli beaker and counted for 5000 s. For tritium analysis by liquid scintillation techniques, 6 mL is counted for 100 min. B2.12 Sediment and Beach Surveys Beach sediment samples are collected near the low tide mark, with preference being given to the top 10 mm of the fine sediment characteristic of tidal mud flats. A disposable polyethylene container is used to collect about 1 kg of sample. In addition, direct gamma radiation dose rate measurements are made at each sediment site using a FAG FH 40F2 low range gamma survey meter. The meter is held for one minute at a point one metre above the intertidal surface. After the sediment sample has been collected, this is repeated. The sample is transferred to a disposable aluminum tray for drying at 80 °C. Dried, caked samples are broken into their original free granular form with a porcelain mortar and pestle and sieved through a 0.5 mm mesh to collect the fines for analysis (a 1 mm sieve is used for coarse

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sediments). Approximately 0.25 kg of dried sediment is counted by gamma spectroscopy for 5000 s. B2.13 Seafood The inshore fishery throughout the Maritimes has declined since the OERMP was started in 1982. Some of it has been closed to any kind of harvesting. However, species of local seafood are collected when available from local fishermen. Sampling focuses on fish, lobsters, aquaculture salmon and clams. Some of the areas where clam harvesting is prohibited are sampled with the permission of the Department of Fisheries and Ocean. Other seafood species are more mobile and can sometimes be found throughout the area: crab, periwinkles, scallops, herring, mackerel, dogfish, cod, haddock, sea urchin, mussels, and flounder. The severe restrictions placed on the inshore fishery as well as the depletion of stocks make many of these samples unavailable for periods of time sometimes spanning years. However, whenever they are available an effort is made to collect as many samples as possible. Approximately 0.5 kg of fresh seafood is collected per sample. Approximately 0.25 kg of each sample is prepared for gamma spectroscopy. Lobsters are cooked first, and the edible meat is removed for analysis. Clams, periwinkles, and crab are analysed whole, with a yield factor applied to account for the mass of the inedible shell. Usually the edible portion of fish is analysed, although sometimes the whole fish is analysed. Samples are counted for 5000 s. B2.14 Aquatic Plants Dulse (Rhodymenia palmata), an edible seaweed which is commercially harvested in the area, is collected monthly when available. Other species of seaweed concentrate a wide range of radionuclides, both natural and man-made. This makes them sensitive indicators of radionuclides in the environment even though they are not identified in the pathway to humans. A portion of the seaweed or dulse is put in a calibrated container and weighed. This is counted by gamma spectroscopy for 5000 s. B2.15 Seawater A 4 L sample is collected in a clean polyethylene container. A portion is removed for tritium analysis and the remainder is acidified (15 mL of 70% nitric acid per 4 L sample). For gamma spectroscopy, 3.6 L is measured into a marinelli beaker and counted for 5000 s. For tritium analysis by liquid scintillation techniques, 6 mL is counted for 100 min. If levels of Sr-89,90, indicating one percent of the monthly DRL, are detected in the chemical analysis of the LEM composite, then the seawater is also to be analysed for these radionuclides.

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B2.16 Miscellaneous Samples This category encompasses all of those samples collected that do not fall within the other categories. It is a mechanism by which the lab can track and evaluate media for potential inclusion in the program. It gives the program flexibility and freedom and encourages the scientific curiosity of laboratory staff. A few of the media types started out this way. As many as 50 samples per year are analysed, including deer liver, mud puddles, snow, sea urchin and mussels. B2.17 Bore Holes A 4 L sample of water is pumped out of the bore hole into a clean polyethylene container. A portion is removed for tritium analysis and the remainder is acidified (15 mL of 70% nitric acid per 4 L sample). For gamma spectroscopy, 3.6 L is measured into a marinelli beaker and counted for 5000 s. For tritium analysis by liquid scintillation techniques, 6 mL is counted for 100 min. B2.18 Parshall Flume PLNGS staff collect a 4 L sample of water from the Parshall flume systems. A portion is removed for tritium analysis, and the remainder is acidified (15 mL of 70% nitric acid per 4 L sample). Of this, 3.6 L is measured into a marinelli beaker for gamma spectroscopy. For tritium analysis, a 6 mL sample of water is counted for 100 min by liquid scintillation techniques. For gamma spectroscopy, the sample is counted for 5000 s. B2.19 Hemlock Knoll Regional Sanitary Landfill In December 1999, PLNGS began disposing of its non-active waste at the public landfill facility. A monitoring program was established prior to the first shipment. It includes sampling of water from the leachate, bore holes and various holding ponds; and dosimeter placement at key locations. Although some extra precautions are observed due to the potential biohazard of some of these samples, they are analysed according to established procedures previously described.

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Appendix C: Location Codes

A 5m PLNGS Dry Fuel Storage Facility - 5 m NNE from perimeter fence



A 20m PLNGS Dry Fuel Storage Facility – 20 m NNE from perimeter fence






A01R Bocabec – GPS Reading – L 45˚ 10.111N, Lo 67˚ 0.378 W

A02R Bocabec – field across from A01R

A03R Bocabec – inter-tidal zone

A04 Bayside – Farm

A05R Letete

A06 Digdeguash

A07 Beaver Harbour

A08 Back Bay

A09 Chamcook

A10R Grand Manan

A11 Oak Bay / Waweig

A12 St. Andrews

A13R St. Andrews environmental monitoring station

A15 Deer Island

A20 Campobello Island

AECL Atomic Energy of Canada Ltd., Chalk River (QA)

ANA Eckert & Ziegler Analytics (QA)

B 5m PLNGS Dry Fuel Storage Facility – 5 m WNW from perimeter fence










B01 New River Beach - inter-tidal zone

B02 Pocologan

B03 New River Beach - park

B04 New River Harbour to Pocologan Harbour

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B10 Pennfield

BAXR Baxter's Dairy

BB PLNGS – Boiler Blow-down

BD Belledune GS

C01 Lepreau Harbour – intertidal zone

C03 Lepreau

CC Coleson Cove GS

CCW PLNGS – Condenser Cooling Water Duct

CH Chatham GS

COG Kinectrics (CANDU Owners Group)

D01 Little Lepreau Basin - inter-tidal zone (remnants of clam shack)

D02 Little Lepreau

D03 Little Lepreau – GPS Reading – L 45˚ 08.030 N , Lo 66˚ 27.686 W

D04 Little Lepreau Basin – inter-tidal zone (remnants of boat wreck)

DH Dalhousie GS

DOE US Department of Energy (QA)

DUMP PLNGS – onsite landfill

DWC PLNGS – drinking water fountains

E01 Maces Bay –GPS Reading–L 45˚ 06.306 N, Lo 66˚ 28.651 W

E02 Maces Bay – Fundy Senior Citizens Centre

E03 Maces Bay – inter-tidal zone

E04 Maces Bay Cemetery

E05 Fundy Shores Elementary School – outside (Thompson/Trynor’s Field)

E06 Fundy Shores Elementary School – inside

E07 Near intersection of route 790, Maces Bay Rd. and County Line Rd.

E11 28 Ridge Rd., Dipper Harbour





EDU Edutech Enterprises

EPA US Environmental Protection Agency (QA)

ERA Environmental Resource Associates

F01 Welch Cove–GPS Reading–L 45˚ 04.782N, Lo 66˚ 27.986 W

F02 Welch Cove – inter-tidal zone

F03 190 Welch Cove Rd., Maces Bay

F04 195 Welch Cove Rd., Maces Bay

F05 181 Ridge Rd., Maces Bay



G01 Indian Cove – inter-tidal zone

G02 Point Lepreau – lighthouse

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G03 offshore – within 2 km of Point Lepreau lighthouse

G04 PLNGS – inter-tidal zone 1 km south of CCW out-fall

GEM PLNGS – Gaseous Effluent Monitor

GL Grand Lake GS

H01 Duck Cove – duck pond

H02 offshore – close to PLNGS condenser cooling water out-fall

H03 Duck Cove - inter-tidal zone

H04 PLNGS – across the road from old site of Information Centre building

H05 PLNGS - start of nature trail near old site of Information Centre trailers

HS Hanson Stream Reservoir

I00 PLNGS SRWMF Phase 1– general site area

I01 PLNGS SRWMF Phase 1

I02 PLNGS SRWMF Phase 2

I03 PLNGS SRWMF Phase 2 – general site area

I04 SRWMF Phase 3

I05 SRWMF Phase 3, General Site Area

I10A PLNGS SRWMF Phase 1 Bore Hole A (BHA)

I10B PLNGS SRWMF Phase 1 Bore Hole B (BHB)

I10C PLNGS SRWMF Phase 1 Bore Hole C (BHC)

I10D PLNGS SRWMF Phase 1 at I01 Barn (Shallow Bore Hole)

I10E PLNGS SRWMF Phase 1 at I01 Barn (Deep Bore Hole)

I10F PLNGS SRWMF Phase 1 Bore Hole southeast from C structure

I10G FUTURE BORE HOLE

I10H FUTURE BORE HOLE

I10I FUTURE BORE HOLE

I11A PLNGS SRWMF Phase 1 - south fence (east side)

I11B PLNGS SRWMF Phase 1 - south fence (centre)

I11C PLNGS SRWMF Phase 1 - south fence (west side)

I11D PLNGS SRWMF Phase 1 - west fence (south side)

I11E PLNGS SRWMF Phase 1- west fence (centre)

I11F PLNGS SRWMF Phase 1 - west fence (north side)

I11G PLNGS SRWMF Phase 1 - north fence (west side)

I11H PLNGS SRWMF Phase 1 - north fence (centre)

I11I PLNGS SRWMF Phase 1 - north fence (east side)

I11J PLNGS SRWMF Phase 1 - east fence (north side)

I11K PLNGS SRWMF Phase 1 - east fence (centre)

I11L PLNGS SRWMF Phase 1 - east fence (south side)

I11M SRWMF Phase 1 ext, Fence W-N

I11N SRWMF Phase 1 ext, Fence W-NN

I11O SRWMF Phase 1 ext, Fence N-W

I11P SRWMF Phase 1 ext, Fence N-C

I11Q SRWMF Phase 1 ext, Fence N-E

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I11S SRWMF Phase 1 ext, Fence E-NN

I11T SRWMF Phase 1 ext, Fence E-N

I1A1 PLNGS SRWMF Phase 1 – Cell 1A1

I1A2 PLNGS SRWMF Phase 1 – Cell 1A2

I20A PLNGS SRWMF Phase 2 – well #4 (shallow) BH4

I20B PLNGS SRWMF Phase 2 – well #4 (deep) BH4

I20C PLNGS SRWMF Phase 2 - well #7 (shallow) BH7

I20D PLNGS SRWMF Phase 2 - well #7 (deep) BH7

I20E PLNGS SRWMF Phase 2 – well #6 (shallow) BH6

I20F PLNGS SRWMF Phase 2 - well #6 (deep) BH6

I20G PLNGS SRWMF Phase 2 – well #5 (shallow) BH5

I20H PLNGS SRWMF Phase 2 – well #5 (deep) BH5

I20I PLNGS SRWMF Phase 2 – well #2 (shallow) BH2

I20J PLNGS SRWMF Phase 2 - well #2 (deep) BH2

I20K PLNGS SRWMF Phase 2 - well #3 (shallow) BH3

I20L PLNGS SRWMF Phase 2 – well #3 (deep) BH3

I20M PLNGS SRWMF Phase 2 – well #1 (shallow) BH1

I20N PLNGS SRWMF Phase 2 – well #1 (deep) BH1

I20P PLNGS SRWMF Phase 2 – north from bore hole 1

I20Q PLNGS SRWMF Phase 2 – south from bore hole 2 (shallow)

I20S PLNGS SRWMF Phase 2 – south from bore hole 2 (deep)

I20T PLNGS SRWMF Phase 2 – north from bore hole 2

I20U PLNGS SRWMF Phase 2 – well #8 shallow (BH8)

I20V PLNGS SRWMF Phase 2 – well #8 deep (BH8)

I20W SRWMF Phase 2, Middle NE Shallow

I21A PLNGS SRWMF Phase 2 – Periphery – south fence (east side)

I21B PLNGS SRWMF Phase 2 - Periphery – south fence (centre)

I21C PLNGS SRWMF Phase 2 - Periphery – south fence (west side)

I21D PLNGS SRWMF Phase 2 - Periphery – west fence (south side)

I21E PLNGS SRWMF Phase 2- Periphery - west fence (centre)

I21F PLNGS SRWMF Phase 2 - Periphery - west fence (north side)

I21G PLNGS SRWMF Phase 2 – Periphery – north fence (west side)

I21H PLNGS SRWMF Phase 2 - Periphery – north fence (centre)

I21I PLNGS SRWMF Phase 2 - Periphery – north fence (east side)

I21J PLNGS SRWMF Phase 2 – Periphery – east fence (north side)

I21K PLNGS SRWMF Phase 2 – Periphery – east fence (centre)

I21L PLNGS SRWMF Phase 2 - Periphery – east fence (south side)

I30A SRWMF Phase 3, Well 1

I30B SRWMF Phase 3, Well 2 Shallow

I30C SRWMF Phase 3, Well 2 Deep

I30D SRWMF Phase 3, Well 3

I30E SRWMF Phase 3, Well 4

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I30F SRWMF Phase 3, Well 5 Shallow

I30G SRWMF Phase 3, Well 5 Deep

I30H SRWMF Phase 3, Well 6

I30I SRWMF Phase 3, Well 7

I30J SRWMF Phase 3, Well 8 Shallow

I30K SRWMF Phase 3, Well 8 Deep

I31A SRWMF Phase 3, Fence S-E

I31B SRWMF Phase 3, Fence S–C

I31C SRWMF Phase 3, Fence S-W

I31D SRWMF Phase 3, Fence W-SS

I31E SRWMF Phase 3, Fence W-S

I31F SRWMF Phase 3, Fence W-SC

I31G SRWMF Phase 3, Fence W-NC

I31H SRWMF Phase 3, Fence W-N

I31I SRWMF Phase 3, Fence W-NN

I31J SRWMF Phase 3, Fence N-W

I31K SRWMF Phase 3, Fence N-E

I31L SRWMF Phase 3, Fence N-C

I31M SRWMF Phase 3, Fence E-NN

I31N SRWMF Phase 3, Fence E-N

I31P SRWMF Phase 3, Fence E-NC

I31Q SRWMF Phase 3, Fence E-WC

I31S SRWMF Phase 3, Fence E-W

I31T SRWMF Phase 3, Fence E-WW

I70 PLNGS – woods between plant & SRWMF

I71 PLNGS - Near Plant Monitoring Well MW01-10, northeast from RB

I75 PLNGS – north 73° east, 85 m from the stack (on pole)

I86 PLNGS – 2nd pole from SRWMF driveway heading toward outer gate

I87 PLNGS –3rd pole from SRWMF driveway heading toward outer gate

I88 PLNGS – 4th pole from SRWMF driveway heading toward outer gate

I89 PLNGS -5th pole from SRWMF driveway heading toward outer gate

I90 At distribution line on west side of Point Lepreau Rd.

I91 100 m north of distribution line on west side of Point Lepreau Rd.





I96 on the old Dupont warning sign at the end of the old “dynamite road”

I97 on the west side of the clearing at the end of the old “dynamite road”

I98 PLNGS – north of SRWMF PHASE 2 (200 m north of transmission line)

I99 PLNGS – north of SRWMF PHASE 2 – (100 m north of transmission

IAEA International Atomic Energy Agency (QA)

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J00 PLNGS – south, 180 m from the stack (on fence)

J01 PLNGS - Near Plant Monitoring Well MW01-1, near surge shaft

J02A PLNGS - Near Plant Monitoring Well MW01-2 (shallow), SSE from

J02B PLNGS - Near Plant Monitoring Well MW01-2 (deep), SSE from RB

J20 PLNGS – south 19° east, 115 m from the stack (on fence)

J35 PLNGS – south 34° east, 135 m from the stack (on sign)

J70 PLNGS – south 69° east, 70 m from the stack (on pole)

K00 PLNGS - Near Plant Monitoring Well MW01-3 south from RB

K01 PLNGS – 95 m west of south gate leading to the lighthouse

K02 PLNGS Cooling Water Pump-house – east fence near surge shaft

K03 PLNGS - Near Plant Monitoring Well MW01-4 SSW from RB

K03C PLNGS sewage lagoon (chlorine contact tank)

K03E PLNGS inactive drainage (east lagoon)

K03W PLNGS inactive drainage (west lagoon)

K04 PLNGS - Near Plant Monitoring Well MW01-5, WSW from RB

K10 Firing Range

KDRP KD Radpro

L01 PLNGS – site of old cement plant

L02 PLNGS – switchyard

L03 PLNGS – outer security building (main gate)

L04 PLNGS – construction stores

L05 PLNGS - Near Plant Monitoring Well MW01-6, WNW from RB

L06 PLNGS - Near Plant Monitoring Well MW01-7, paved staff parking

L07 PLNGS - Near Plant Monitoring Well MW01-8, construction parking

L08 PLNGS - Near Plant Monitoring Well MW01-9, N beyond fire

L09A MW05-1, fire fighter training area

L09B MW05-2, fire fighter training area

L09C MW05-3, fire fighter training area

L09D MW05-4, fire fighter training area

L09E MW05-5, fire fighter training area

L10A Landfill SW05-1

L10B Landfill SW05-2

L10C Landfill SW05-3

L10D Landfill SW05-4

L10E Landfill SW05-5

L10F Landfill SW05-6

L10G Landfill Seep

L11A Landfill MW6

L11B Landfill MW7

L11C Landfill MW8

L11D Landfill MW9

L11E Landfill MW10

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L11F Landfill MW11

L11G Landfill MW12

L11H Landfill MW13

LAB Fredericton – Health Physics Laboratory

LEM PLNGS – Liquid Effluent Monitor

M02 PLNGS – Administration Building (2nd floor)

MISC Miscellaneous locations

MQ Mactaquac GS

N01 Dipper Harbour – GPS Reading – L 45˚ 05.399 N, Lo 66˚ 25.154 W



N04 Dipper Harbour – intertidal zone

N05 Dipper Harbour – beach behind restaurant

N06 Dipper Harbour – offshore

NTS Nuclear Technology Services Inc. (QA)

P01 Chance Harbour – GPS Reading – L 45˚ 07.494 N, Lo 66˚ 21.456 W

P02 Little Dipper Harbour

P03 Liberty Hill – GPS Reading – L 45˚ 07.043 N, Lo 66˚ 21.498

P04 Round Meadow Farm

P05 Chance Harbour – 2 km offshore

PLNGS PLNGS – general

Q01R Lorneville

RPB Radiation Protection Bureau, Health Canada (QA)

RPC Research and Productivity Council

S00 Saint John and surrounding area

S10 Hammond River

SPL Spruce Lake reservoir

TAYR Taymouth

X03R Fredericton - Chestnut Complex lab

X04R Fredericton – reference seafood

X05R Fredericton – reference milk test

X06R West of Fredericton (Silverwood)

X10 Fredericton Junction – Atlantic Dairy Institute

X12 York Mills

Y##### Hemlock Knoll Regional Sanitary Landfill

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Appendix D: Abbreviations CCW Condenser Cooling Water CL Critical Level CNSC Canadian Nuclear Safety Commission COG CANDU Owners Group CSA Canadian Standards Association DRL Derived Release Limit FWHM Full Width Half Maxima GEM Gaseous Effluent Monitor IAEA International Atomic Energy Agency ISO International Organization for Standardization LEM Liquid Effluent Monitor LLD Lower Limit of Detection LSC Liquid Scintillation Counter MFC Mass Flow Controller NBEMO New Brunswick Emergency Measures Organization NIST National Institute of Standards and Technology NRC National Research Council NTS Nuclear Technology Services OERMP Operational Environmental Radiation Monitoring Program PICA Problem Identification and Corrective Action PLNGS Point Lepreau Nuclear Generating Station QA Quality Assurance QC Quality Control REPD Radiation and Environmental Protection Division RPB Radiation Protection Bureau SEA Significant Environmental Aspect SRWMF Solid Radioactive Waste Management Facility TLD Thermoluminescent Dosimeter USDOE United States Department of Energy

ENVIRONMENTAL PROTECTION -2016 ACR-07000-2016 Rev. 0 · ENVIRONMENTAL PROTECTION -2016...

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